ML25345A432
| 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 Cleve Reasoner, Senior Vice President and Chief Nuclear Officer Wolf Creek Nuclear Operating Corp.
P.O. Box 411 Burlington, KS 66839
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.
C. Reasoner 2
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 cc w/ encl: Distribution via LISTSERV Signed by Agrawal, Ami on 12/15/25
SUNSI Review By: CMH
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RI:DORS/PBB SRI:DORS/PBB SPE:DORS/PBB BC:DORS/PBB NAME CSigel CHenderson MBloodgood AAgrawal SIGNATURE
/RA/
/RA/
/RA/
/RA/
DATE 12/12/25 12/12/25 12/15/25 12/15/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000482 License Number:
NPF-42 Report Number:
05000482/2025003 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
2
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: 71114.04.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 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, 2025.
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)
4 (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
5 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, 2025 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 Sample)
(1)
July 1, 2024, through June 30, 2025
6 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) (1 Sample)
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 10039349 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.
7 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Corrective Action Documents Condition Report (CR) 10042607 71111.04 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 5
Corrective Action Documents Condition Report (CR) 10042302, 10042589 Drawings KD-7496 One Line Diagram 82 E-1F9905 Fire Hazard Analysis 14 PT115374 Scaffolds Blocking Spray Pattern On Aux 2000 Hallways 0
PT116227 Fire Permit 0
PT116616 Breach GLD0098 for Temp A RCP Cooling 0
PT116621 Combustible Materials to Support TMO 25-003-BG 0
WCNOC-PSA-067 Internal Fire - Qualitative Screening, Quantitative Screening and Quantification Notebook 3
Miscellaneous WCNOC-PSA-076 Wolf Creek Generating Station PRA Internal Fire -
Qualitative Screening, Quantitative Screening and Quantification Notebook 3
ALR KC-888 Fire Protection Panel KC-008 Alarm Response 36 AP 10-102 Control of Combustible Materials 28 AP 10-103 Fire Protection Impairment Control 42 AP 10-104 Breach Authorization 42 AP 10-106 Fire Preplans 26 OFN KC-016 Fire Response 54 SYS FP-012 Operation of the CWSH Fire Protection Panel 1
71111.05 Procedures WCRE-35 Boundary Matrix 13 Corrective Action Documents Condition Report (CR) 10039173, 10039177, 10041227, 10041250, 10041364, 10042465 71111.12 Corrective Action Documents Resulting from Inspection Condition Report (CR) 10041810
8 Inspection Procedure Type Designation Description or Title Revision or Date M-0022 P&ID Plant Service Water System (WS) 51 M-12EA01 Piping and Instrumentation Diagram Service Water System 22 M-12EA02 Piping and Instrumentation Diagram Service Water System 29 M-12EF01 Piping Instrumentation Diagram Essential Svc Water System 30 Drawings M-12EF02 Piping and Instrumentation Diagram Essential Service Water System 46 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 0
ALR 00-081A Two/More Rods at Bottom 9
AP 22B-001 Outage Risk Management 24 BD-EMG E-0 Reactor Trip or Safety Injection 33 EMG E-0 Reactor Trip or Safety Injection 48 EMG E-1 Loss of Reactor or Secondary Coolant 32A EMG E-2 Faulted Steam Generator Isolation 25 EMG ES-03 SI Termination 29 OFN SF-011 Realignment of Dropped, Misaligned Rod(s) and Rod Control Malfunctions 14 STS IC-740A RHR Switchover to Recirc Sump Test - Train A 34 STS PE-154 LLRT Valve Lineup for Penetration 54 7
71111.13 Procedures SYS NN-332 Deenergizing NN Buses 18 AN-07-009 Gothic Model for CCW Pump Room Temperature 1
GL-03-W Auxiliary Building HVAC 1
GL-M-007 Calculate cooling loads in SR pump rooms post LOCA 0
Calculations GL-M-007 Calculate Cooling Load in SR Pump Rooms Post LOCA:
1107, 1108, 1109, 1110, 1111, 1112, 1113, 1114, 1401, 1406 0
Corrective Action Documents Condition Report (CR) 10042197, 10042295, 10043589 71111.15 Corrective Action Documents Resulting from Condition Report (CR) 10042627, 10043597, 10043600
9 Inspection Procedure Type Designation Description or Title Revision or Date Inspection E-13AL08 Schematic Diagram Instrumentation and Alarms (SH 3) 2 M-12BB01 Piping and Instrumentation Diagram Reactor Coolant System 49 M-12BB02 Piping and Instrumentation Diagram Reactor Coolant System 39 M-12BG01 Piping and Instrumentation Diagram Chemical and Volume Control System 26 M-12BG02 Piping and Instrumentation Diagram Chemical and Volume Control System 19 M-12BG03 Piping and Instrumentation Diagram and Volume Control System 53 M-12BG05 Piping and Instrumentation Diagram Chemical and Volume Control System 28 Drawings M-12EM02 Piping and Instrumentation Diagram High Pressure Coolant Injection System 25 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 0
ALR 00-129A MD AFP A Trouble 8
AP 26C-004 Operability Determinations and Functionality Assessments 48 BD-EMG E-0 Reactor Trip or Safety Injection 33 EMG E-0 Reactor Trip or Safety Injection 48 EMG E-1 Loss of Reactor or Secondary Coolant 32A EMG ES-02 Reactor Trip Response 42 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) 43 STS AL-101 MDAFW Pump A Inservice Pump Test 46 STS KJ-001A Integrated D/G and Safeguards Actuation Test - Train A 73A SYS BG-200 Reactor Makeup Control System Normal Operation 53 Procedures SYS EG-120 Component Cooling Water System 44
10 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, 22-478391-000, 22-479779-000, 22-480431-000, 22-481688-000, 22-482296-000, 22-483479-000 Calculations SA-90-056 Reactor Protection System/Engineered Safety Features Actuation System Channel Error Allowances 0
Corrective Action Documents Condition Report (CR) 10042365, 10042383, 10042915, 10042983 M-12BB03 Piping and Instrumentation Diagram Reactor Coolant System 20 M-12BG01 Piping and Instrumentation Diagram Chemical and Volume Control System 26 Drawings M-763-00369 Power Supplies, Phase Sense and Multiplex Control W3 Engineering Changes DECP 25-002-SF Rod Control Temporary Power Supply 0
M-763-00872 Westinghouse Rod Control System Corrective Maintenance Guide W3 ODMI 2025-03 Elevated A RCP #1 Seal Leak Off Rate 0
PT116615 Temp Mod for RCP A Seal Cooling inch Pen Seals P131W1309 and P131W1310 0
PT116702 Breach Door 13322 to Run a Fill Hose for RCP Seal Temp.
Chiller 0
WCAP-15360-P Westinghouse Rod Control System Corrective Maintenance Guide 6
Miscellaneous WCAP-17746-P Westinghouse Setpoint Methodology as Applied to the Wolf Creek Generating Station 0
AP 05-005 Design, Implementation, and Configuration Control of Modifications 28 AP 21I-001 Temporary Configuration Changes 16B OFN BB-005 RCP Malfunctions 38 TMO 25-003-BG A RCP #1 Seal Injection Heat Exchanger 00 Procedures TMP 25-005 Temporary Chiller for RCP A Seal Injection 0, 1 71111.18 Work Orders WO 133185, 135106, 135110, 137150, 137153 71111.24 Corrective Action Documents Condition Report (CR) 10042790, 10043792
11 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 2
M-12BG01 Piping and Instrumentation Diagram Chemical and Volume Control System 26 M-12BG02 Piping and Instrumentation Diagram Chemical and Volume Control System 19 M-12BG03 Piping and Instrumentation Diagram and Volume Control System 53 M-12BG05 Piping and Instrumentation Diagram Chemical and Volume Control System 28 M-12EF01 Piping and Instrumentation Diagram Essential SCV Water System 30 M-12EM02 Piping and Instrumentation Diagram High Pressure Coolant Injection System 25 Drawings M-12GK01 Piping and Instrumentation Diagram Control Building HVAC 16 AP 23L-002 Heat Exchanger Program 6
AP 26C-004 Operability Determinations and Functionality Assessments 48 CKL EF-120 Essential Service Water Valve, Breaker and Switch Lineup 57 EMG E-0 Reactor Trip or Safety Injection 48 EMG E-1 Loss of Reactor or Secondary Coolant 32A EMG ES-02 Reactor Trip Response 42 EMG ES-04 Natural Circulation Cooldown 24A MPE GK-003 Control Room and Class 1E A/C Units Preventive Maintenance Activity 8
MPE GK-004 GK Unit Preparation for Work 13 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 35 Procedures STS GK-002B Control Room A/C Unit Operability Test 3
12 Inspection Procedure Type Designation Description or Title Revision or Date SYS BG-200 Reactor Makeup Control System Normal Operation 53 SYS BG-206 Boric Acid System Operation 51 WCRE-08 WCGS Fuse List 34 Work Orders WO 89326, 102014, 102016, 102022, 128458, 132840, 132455, 340653, 15-404306-016 Miscellaneous WCNOC-163 Mitigating System Performance Index (MSPI) Basis Document 14 AP 22C-003 On-Line Nuclear Safety and Generation Risk Assessment 30 AP 23M-001 WCGS Maintenance Rule Program 14 Procedures SYS KJ-123 Post Maintenance Run of Emergency Diesel Generator A 77 71151 Work Orders WO 79662 Corrective Action Documents Condition Report (CR) 10039304 E-11NK01 Class 1E 125V DC System Meter and Relay Diagram 22 E-11NK02 Class 1E 125V DC System Meter and Relay Diagram 21 Drawings E-13AB29 Schematic Diagram Main Steam Isolation Valves Control -
Part 2 5
ALR 00-025C NK01 Trouble 13A ALR 301 124 VDC Class 1E Switchboard NK01 11 EMG C-0 Loss of All AC Power 46A EMG E-0 Reactor Trip or Safety Injection 48 OFN NB-030 Loss of AC Emergency Bus NB01 (NB02) 43 OFN NK-020 Loss of Vital125 VDC Bus NK01 NK02 NK03 NK04 14 OFN NK-021 Loss of Vital 120 VAC Instrumentation Bus 31A SYS GK-122 Manual CRVIS Line-Up 26 71152A Procedures SYS NN-332 Deenergizing NN Buses 18