IR 05000482/2024002

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Integrated Inspection Report 05000482/2024002
ML24200A177
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 07/18/2024
From: Greg Werner
NRC/RGN-IV/DORS/PBB
To: Reasoner C
Wolf Creek
Werner G
References
IR 2024002
Download: ML24200A177 (1)


Text

July 18, 2024

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2024002

Dear Cleve Reasoner:

On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On July 9, 2024, the NRC inspectors discussed the results of this inspection with R. Bayer, General Manager, Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

Three findings of very low safety significance (Green) are documented in this report. All of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations 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.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; 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, Gregory E. Werner, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket No.

05000482

License No.

NPF-42

Report No.

05000482/2024002

Enterprise Identifier:

I-2024-002-0009

Licensee:

Wolf Creek Nuclear Operating Corp.

Facility:

Wolf Creek Generating Station

Location:

Burlington, KS

Inspection Dates:

April 1 through June 30, 2024

Inspectors:

G. Birkemeier, Resident Inspector

N. Greene, Senior Health Physicist

C. Henderson, Senior Resident Inspector

J. Mejia, Reactor Inspector

J. Melfi, Project Engineer

D. Proulx, Senior Project Engineer

B. Tharakan, Technical Assistant

Approved By:

Gregory E. Werner, 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.

List of Findings and Violations

Failure to Adequately Barricade and Post a High Radiation Area Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-01 Open/Closed

[H.8] -

Procedure Adherence 71124.01 The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation of Technical Specification 5.7.1.a, High Radiation Areas, when the licensee failed to adequately barricade and conspicuously post a high radiation area on the 2000-foot elevation of the containment. Specifically, on April 11, 2024, while performing a walk down in the containment, the NRC inspector identified an area outside of a posted and barricaded high radiation area that had accessible dose rates in excess of 100 millirem per hour.

Failure to Follow Licensee Procedures and Implement High Contamination Area Controls Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-02 Open/Closed

[H.11] -

Challenge the Unknown 71124.01 The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation of Technical Specification 5.4.1.a, Procedures, as recommended in Regulatory Guide 1.33, revision 2, appendix A, February 1978, when the licensee failed to adequately implement high contamination area controls for a job activity. Specifically, on April 8, 2024, at least two workers, a welder, and a pipefitter, were exposed to high contamination conditions of 300,000 disintegrations per minute per 100 square centimeters (dpm/100cm2) while performing weld preparation associated with the replacement of train A residual heat removal drain valves EJV0169 and EJV0007 on the pump suction line. As a result, two workers were contaminated and had to be evaluated for unintended internal dose.

Failure to Perform a Radiation Survey to Identify the Magnitude and Extent of Changing Radiological Conditions Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-03 Open/Closed

[H.1] -

Resources 71124.01 The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation of 10 CFR 20.1501(a) when the licensee failed to survey an area with changing radiological conditions. Specifically, on April 2, 2024, during activities associated with refueling outage 26, the licensee withdrew the incore detector thimbles and failed to survey the area above and around the entrance to the incore tunnel to identify the extent and magnitude of the changing radiation levels. As a result, workers in the high radiation area were not informed about elevated radiation levels as high as 240 millirem per hour at 30 centimeters from the incore tunnel entrance.

Additional Tracking Items

None.

PLANT STATUS

Wolf Creek Generating Station began the inspection period shutdown for refueling outage 26, which began on March 28, 2024. On May 10, 2024, the unit commenced reactor startup, and the reactor was made critical. The unit returned to full power on May 14,

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

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of a tornado/missile for the following systems:
  • refueling water storage tank on June 12, 2024

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1)containment recirculation sump recovery path on April 10, 2024 (2)train A component cooling water system on April 25, 2024 (3)train B offsite circuit to train B safety-related 4160-volt bus (NB02) on April 30, 2024 (4)train B containment coolers on April 30, 2024 (5)train B residual heat removal (RHR) system fire in the control room actions on April 30, 2024 Type text here

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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)reactor building 2000-foot elevation inside the secondary shield wall, fire area RB-1 and RB-2, on April 2, 2024 (2)reactor building 2026-foot elevation, fire area RB-3, RB-4, RB-7, and RB-8 on April 2, 2024 (3)reactor building 2068-foot elevation, fire area RB-6, on April 16, 2024 (4)reactor building area within primary shield wall, fire area RB-10, on April 16, 2024 (5)reactor building 2047-foot elevation, fire area RB-5 and RB-10, on April 17, 2024 (6)communication corridor fire doors being held open during alternate ventilation lineup, fire area CC-1, on April 23, 2024 (7)south electrical penetration room damaged fireproofing, fire area A-17, on May 7, 2024

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) train A component cooling water heat exchanger performance analysis on April 2, 2024

===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities during refuel outage 26, from April 1 to May 23, 2024.

PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination
  • accumulator safety injection, EP-01-MW7152, pipe to valve
  • chemical volume control system, BG-02-S056-A, tee to pipe
  • chemical volume control system, BG-21-F027A, pipe to pipe
  • control rod drive mechanism, CH-213-112-C, nozzle to housing
  • control rod drive mechanism, CH-214-112-B, nozzle to housing
  • control rod drive mechanism, CH-214-112-G, nozzle to housing
  • control rod drive mechanism, CH-215-112-C, nozzle to housing
  • RHR, EJ-04-F043, pipe to valve
  • RHR, EJ-04-F048A, pipe to valve
  • reactor vessel closure head Bolting, CH-STUDS-1 thru 54, closure head studs (54)
  • reactor vessel closure head, RBB01, CH-101-104-A, shell to shell
  • reactor vessel closure head, RBB01, CH-101-104-B, shell to shell
  • reactor vessel closure head, RBB01, CH-101-104-C, shell to shell
  • reactor vessel closure head, RBB01, CH-101-104-D, shell to shell
  • reactor vessel closure head, RBB01, CH-103-101, dome to shell, one recordable indication being tracked, no change, indication allowable per ASME Sec XI, IWB-3510.

Visual Examination

  • fuel pool cooling, EEC01A-SUP-1, heat exchanger support
  • fuel pool cooling, EEC01A-SUP-2, heat exchanger support
  • fuel pool cooling, EEC01A-SUP-3, heat exchanger support
  • component cooling water, PEG01A-SUP-1, pump support
  • reactor vessel closure head, RBB01, bare metal head surface
  • reactor vessel internals, upper internals, core barrel, lower internals Magnetic Particle Examination

safety injection system, EMV0066 & EMV0136 valves and piping, W-1A, W-2, W-3A, W-4A, W-5A, W-6A, W-7A o

RHR system, EJV0007 & EJV0169 valves and piping, BW-1, BW-2A, BW-3A, BW-4, SW-1A, SW-2, SW-3A PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) Reviewed video of reactor vessel head penetrations 1, 3, 7, 8, 12, 16, 18, 22, 25, 31, 32, 34, 37, 39, 40, 43, 54, 56, 60, 62, 64, 67, 71, 73, 76, 78, and general head area.

PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1)boric acid evaluations and screenings:

  • Condition report (CR) 10031941 EMV0053
  • CR 10031946 BBV0261
  • CR 10031947 BBV0241
  • CR 10031948 BBPI001
  • CR 10031949 BBLT0462
  • CR 10031953 BBFI0033
  • During walkdown, indications of refueling cavity liner leaks through concrete were observed.

PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)

The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:

(1) A 100 percent full length eddy current inspection of all tubes, with bobbin coil probe, in steam generators A, B, C and D. A total of 45 tubes were plugged, which included 4 tubes in steam generator A, 20 tubes in steam generator B, 12 tubes in steam generator C, and 9 tubes in steam generator D. One tube from steam generator A had an axial indication of outside diameter stress corrosion cracking, located at a dent located at the seventh support plate on the cold leg side, and was plugged.

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 plant startup from refueling outage 26 and low power reactor physics testing on May 10, 2024.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated just-in-time training for plant startup from refueling outage 26 on April 30, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1)steam generator atmospheric relief valve and turbine-driven auxiliary feedwater pump flow control valve nitrogen accumulator system maintenance effectiveness on May 16, 2024 (2)spent fuel pool cooling maintenance effectiveness on June 10, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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)emergent activities for the loss of train A safety-related 4160-volt bus during load shedder and emergency load sequencers card replacement on April 8, 2024 (2)turbine-driven auxiliary feedwater pump overspeed failure emergent work activities on May 8, 2024 (3)train B essential service water from component cooler water B heat exchanger isolation valve failed fire protection surveillance testing emergent work activities or May 30, 2024 (4)train A 4kV degraded voltage time delay relay failure emergent work activities on June 12, 2024 (5)ultimate heat sink dredging activities on June 26, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1)train B essential service water piping leak from a weld above drain valve EFV0278 operability determination on April 30, 2024 (2)turbine-driven auxiliary feedwater pump steam generator A flow control valve with a nitrogen leak on the associated atmospheric relief valve operability determination on May 15, 2024 (3)train A safety-related 4160-volt station blackout supply breaker 114 failed to closed during surveillance testing past operability determination on June 11, 2024 (4)train A centrifugal pump coupling grease leakage operability determination on June 11, 2024 (5)emergency diesel generator B number 8-cylinder abnormal low firing pressure and high exhaust temperature operability determination on June 30, 2024

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)startup transformer replacement on April 23, 2024 (2)removal of flux thimble at reactor location L-8 from service on May 15, 2024

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage 26 from April 1 to May 11, 2024.

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) (8 Samples)

(1)emergency diesel generator A maintenance post-maintenance testing on April 18, 2024 (2)containment cooler D motor replacement post-maintenance testing on April 28, 2024 (3)startup transformer replacement post-maintenance testing on April 30, 2024 (4)train A RHR maintenance post-maintenance testing on May 1, 2024 (5)train B RHR maintenance post-maintenance testing on May 1, 2024 (6)train A essential service water pump motor replacement post-maintenance testing on May 1, 2024 (7)emergency diesel generator B maintenance post-maintenance testing on May 15, 2024 (8)train A load shedder and emergency load sequencer card replacement post-maintenance testing on May 15, 2024

Surveillance Testing (IP Section 03.01) (3 Samples)

(1)main steam safety valve lift set point testing on May 6, 2024 (2)engineered safety feature actuation system 18-month surveillance test risk-informed documented evaluation on May 7, 2024 (3)low temperature overpressure protection relief valve testing on May 15, 2024

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1)main feedwater bypass regulating valves B and D greater than alert value on June 11, 2024

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1)reactor coolant pump B seal water supply valve, BBHV8351B, on May 14, 2024

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1)reactor coolant system leakage post refueling outage on June 17, 2024

71114.06 - Drill Evaluation

Required Emergency Preparedness Drill (1 Sample)

(1)emergency preparedness drill involving an earthquake causing a loss of offsite power, loss of coolant accident, and a containment leak into auxiliary building on June 18,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructed workers on plant-related radiological hazards and the radiation protection (RP) requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1)physical and programmatic controls for highly activated or contaminated materials (non-fuel) stored within spent fuel pool and other storage pools (2)workers exiting the containment building and performing contamination monitoring during a refueling outage

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Radiation work permit (RWP) 243220, primary side steam generator eddy current testing (S/G A, B, C, D) and zero entry nozzle dam installation and removal
(2) RWP 243200, RP primary & secondary steam generator rover coverage
(3) RWP 246051, reactor vessel lower internals / core barrel removal and re-installation
(4) RWP 242001, welding activities; work order 19-450006 RHR pump A High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas:

(1)very high radiation area - containment building, 2000' in-core tunnel access (2)locked high radiation area - 2047' containment building reactor head scaffolding

(3) HRA - 2031' radwaste building high integrity container filter cask
(4) HRA - 2000' containment building BCHV-8160l letdown piping
(5) HRA - 2000' containment building inside bio-shield steam generator A and C platforms Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1) The inspectors evaluated radiation worker and RP technician performance as it pertains to RP requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1)control building emergency ventilation system A and B trains (FGK02A and FGK02B)

(2)technical support services emergency ventilation system (VTF-1)

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1)high efficiency particulate air (HEPA) filtration systems used on the steam generator A, B, C and D work in containment.

(2) HEPA filtration system and decontamination tent used during steam generator stud cleaning.

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices. The NRC credits a baseline sample from the International Atomic Energy Agency Operational Safety Review Team review (under section 7.5.6) conducted March 6-23, 2023.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Shipment Preparation (IP Section 03.04)

(1) The inspectors observed the preparation of radioactive shipment 24R09 of low specific activity radioactive material on April 10,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS07: High Pressure Injection Systems (IP Section 02.06)===

(1) April 1, 2023, through March 31, 2024

MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)

(1) April 1, 2023, through March 31, 2024 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
(1) April 1, 2023, through March 31, 2024

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) April 1, 2023, through March 31, 2024

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) July 1, 2023, through March 31, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1) July 1, 2023, through March 31, 2024

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)emergency diesel generator B failure to start in manual due to a failed relay and emergency diesel part 21 on May 28, 2024

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program to identify potential trends in post-maintenance testing planning following corrective and planned maintenance activities that might be indicative of a more significant safety issue.

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)

(1)emergent activities for the loss of train A safety-related 4160-volt bus during load shedding and emergency load sequencing card replacement on April 23,

INSPECTION RESULTS

Failure to Adequately Barricade and Post a High Radiation Area Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-01 Open/Closed

[H.8] -

Procedure Adherence 71124.01 The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation of Technical Specification 5.7.1.a, High Radiation Areas, when the licensee failed to adequately barricade and conspicuously post a high radiation area on the 2000-foot elevation of the containment. Specifically, on April 11, 2024, while performing a walk down in the containment, the NRC inspector identified an area outside of a posted and barricaded high radiation area that had accessible dose rates in excess of 100 millirem per hour.

Description:

On April 11, 2024, inspectors walked down the 2000-foot elevation of containment, near the letdown system containment isolation valve. While using a gamma dose rate survey meter, the inspectors identified general area dose rates of greater than 100 millirem per hour outside of the posted HRA boundary. The containment was generally posted as a radiation area. The inspectors noticed a licensee RP technician in the area and asked him to verify the general area dose rates just surveyed outside of the posted HRA boundary. The RP technician came over and surveyed the area with a Ludlum ion chamber survey meter and confirmed that the dose rates were greater than 100 millirem per hour, as observed by the inspectors. The inspectors then proceeded to exit containment for a scheduled meeting.

Upon exiting containment, the inspectors discussed this issue of concern with a RP supervisor waiting outside of containment. The RP supervisor and a RP tech then proceeded to perform additional surveys to evaluate the issue discussed. The licensee found the accessible higher dose rates appeared to stream from a 7-foot-high letdown piping elbow.

However, these post surveys were conducted after the HRA barricade was moved out from the initial boundary location as identified by the inspectors. After further discussion between NRC and the RP staff, it was determined that the HRA initially identified by the inspectors was not adequately posted and barricaded, as required by the licensee's Technical Specification (TS) 5.7.1 and licensee procedure RPP 02-215, Posting of Radiological Controlled Areas," revision 36A, steps 4.15.1, 5.2.1, 5.2.2, 5.3.4, and 9.1.2.

Procedure RPP 02-215, stated the following, in part:

  • Step 4.15.1: A High Radiation Area is defined as any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 0.1 REM in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters
(cm) from the radiation source or 30 centimeters from any surface that the radiation penetrates.
  • Step 5.2.1: Supervisors of RP ensure that plant areas are properly posted.
  • Step 9.1.2: Posted areas must be clearly and conspicuously marked at all accessible sides and entrances. access points, other than doorways, to either a high radiation area or a locked high radiation area will be conspicuously posted to prevent inadvertent entry into the area.

In this occurrence, the HRA, with dose rates greater than 100 millirem per hour at 30 cm from the source, was not conspicuously posted and adequately barricaded, as required.

Additionally, RP supervision discussed the issue with multiple workers and RP staff and determined that the HRA boundary had been moved or down posted without their approval, as required, prior to the inspectors identifying the HRA dose rates outside of the boundary.

Corrective Actions: Once the HRA dose rates and inadequate posting and boundary were confirmed by RP, RP supervision immediately extended the HRA boundary out approximately 2 feet from its current location, added a steel stanchion, and taped it to the floor to prevent easy removal or movement. These implemented corrective actions established appropriate controls for the HRA posting and barricade. The licensee also coached workers on the requirements to inform RP supervision of moving boundaries, down posting HRAs, and establishing appropriate HRA controls.

Corrective Action References: CRs 10032152 and 10032533

Performance Assessment:

Performance Deficiency: The licensee failed to barricade and conspicuously post an HRA on the 2000-foot elevation of containment.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the program & process attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. Specifically, the failure to barricade and conspicuously post an HRA had the potential for workers to inadvertently enter an HRA without knowledge that the dose rates exceeded 100 mrem per hour and accumulating unintended dose.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix C, Occupational Radiation Safety SDP. The inspectors determined that the finding was of very low safety significance (i.e., Green) because:

(1) it did not involve as-low-as-reasonably achievable planning or work controls,
(2) there was no overexposure,
(3) there was no substantial potential for an overexposure, and
(4) the ability to assess dose was not compromised.

Cross-Cutting Aspect: H.8 - Procedure Adherence: Individuals follow processes, procedures, and work instructions. Specifically, licensee Procedure RPP 02-215 required that HRA boundaries were conspicuously posted and barricaded, that RP supervision ensured that HRAs were posted, and RP supervision approved and was knowledgeable of HRA down postings. However, these requirements were not met when RP supervision determined that the HRA boundary in the 2000-foot elevation of containment had been moved (i.e., down posted) without their knowledge and approval, resulting in an inadequately controlled HRA.

Enforcement:

Violation: Title 10 CFR 20.1901(b), Posting of High Radiation Areas, requires, in part, that the licensee shall post each high radiation area with a conspicuous sign or signs bearing the radiation symbol and the words, CAUTION, HIGH RADIATION AREA, or, DANGER, HIGH RADIATION AREA.

Technical Specification 5.7.1.a, High Radiation Areas, requires, in part, that each entryway to areas with dose rates greater than 100 millirem per hour and not exceeding 1.0 rem per hour at 30 centimeters from the radiation source, or any surface penetrated by the radiation, shall be barricaded and conspicuously posted as an HRA. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

Contrary to the above, on April 11, 2024, the licensee failed to barricade and conspicuously post entryways to a high radiation area with a conspicuous sign or signs bearing the radiation symbol and the words CAUTION, HIGH RADIATION AREA or DANGER, HIGH RADIATION AREA, as required by 10 CFR 20.1901(b) and TS 5.7.1(a). Specifically, an area in the 2000-foot elevation of containment with radiation levels exceeding 100 millirem per hour at 30 cm from the source but did not exceed 1.0 rem per hour at 30 centimeters from the radiation source, or any surface penetrated by the radiation, was not barricaded or posted as a high radiation area, as required.

Type text here

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.

Failure to Follow Licensee Procedures and Implement High Contamination Area Controls Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-02 Open/Closed

[H.11] -

Challenge the Unknown 71124.01 The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation of Technical Specification 5.4.1.a, Procedures, as recommended in Regulatory Guide 1.33, revision 2, appendix A, February 1978, when the licensee failed to adequately implement high contamination area controls for a job activity. Specifically, on April 8, 2024, at least two workers, a welder and a pipefitter, were exposed to high contamination conditions of 300,000 disintegrations per minute per 100 square centimeters (dpm/100cm2)while performing weld preparation associated with the replacement of train A residual heat removal drain valves EJV0169 and EJV0007 on the pump suction line. As a result, two workers were contaminated and had to be evaluated for unintended internal dose.

Description:

After reviewing the assigned radiation work permit (RWP), reviewing survey maps of the work area, and briefly speaking to the welder, the inspectors questioned the licensee about whether the welding activities on RHR piping should have been performed with high contamination area controls in place. On day shift of April 8, 2024, a pipefitter and welder were assigned to grind out a socket weld on the train A RHR suction header drain line containing valves EJV0169 and EJV0007. A HEPA air mover and sampler were already staged in the work area by the night shift workers. The workers were signed onto RWP 24-2001, task 2, Welding Activities. The workers were wearing a full set of protective clothing as required for a contamination area. Intermittent RP coverage was provided.

Upon performing the socket weld, the workers identified that additional RHR piping would need to be accessed due to damaging the piping above the valve EJV0169. Working on this additional piping was a change in their work scope. The pipefitter used a 4-inch grinder to remove the socket weld and a hand-file to dress up the pipe prior to welding. Upon exiting from the radiologically controlled area for the lunch period, the pipefitter was found to have 300 net counts per minute (ncpm) on his beard. He was decontaminated and released. A whole-body count was not immediately performed to assess potential internal exposure at this time. Licensee procedures required a whole-body count if facial contamination is detected. The licensee wrote CR 10031822 for not performing a timely whole-body count.

After lunch, the workers went back to continue with the weld on the RHR piping. The RP technician repositioned the HEPA air mover suction closer to provide better air flow away from the workers. Highly contaminated water was dripping out of the RHR system piping at the rate of one drop per second and was captured on an absorbent pad. The water was interfering with the welding. After performing some welding and spending 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in the work area, the workers exited the area. Radiation protection personnel surveyed the workers and found contamination on the welder. The welder was found to have 40,000 ncpm (i.e., 400,000 dpm/100cm2 with 10-percent efficiency) on his upper front shirt and 500 ncpm on his face. This time, after the welder was decontaminated, he was immediately sent for a whole-body count. Radiation protection personnel provided the inspectors with initial surveys of the area that indicated contamination levels were as high as 2.4 million dpm/100cm2 beta/gamma and 864 beta/alpha ratio. The pipe was decontaminated to 10,000 dpm/100cm2 beta/gamma before work commenced during the dayshift on April 8th.

A follow up survey, M-20240408-25, was performed in the work area. The welders hood was found to have 30,000 dpm/100cm2 beta/gamma, the water and pipe were 300,000 dpm/100cm2 beta/gamma. The welder stated that water continued to drip out of the pipe during their work. Neither the welder nor the RP technician identified this condition as adverse to the protection provided by a single set of protective clothing nor did they stop work until it was confirmed the accessible contamination levels had increased significantly such that the area, they were working in was a high contamination area, which required additional controls. The inspectors determined this was contrary to the RWP procedure, which required they stop work if radiological conditions change or compliance with the RWP requirements can no longer be achieved. Given that highly contaminated water continued to drip from the pipe while the work was ongoing, the inspectors concluded that the radiological conditions had changed and compliance with the RWP requirements was not achieved.

Corrective Actions: The licensee assessed the internal dose of the contaminated welder and pipefitter and determined neither worker received an internal dose. The licensee conducted a review of their procedures for missed opportunities to prevent future personnel contamination events for similar activities. Radiation protection personnel were provided additional training on compliance with RWP requirements and procedures. Workers were coached on refraining from touching their face or clothing while working in contaminated areas and stopping when faced with uncertain or changing conditions.

Corrective Action References: CRs 10031822, 10031829, and 10032535

Performance Assessment:

Performance Deficiency: The failure to establish high contamination area controls when two workers were commencing job activities in radiological conditions exceeding 100,000 dpm/100cm2 was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the program & process attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. Specifically, the licensee's failure to implement high contamination area controls for welding activities on the train A RHR system had the potential to lead to unintended dose for the welder and/or pipefitter and resulted in measured contamination levels as high as 400,000 dpm/100cm2 beta/gamma found on the welder's shirt.

Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix C, Occupational Radiation Safety SDP. The inspectors determined that the finding was of very low safety significance (i.e., Green) because:

(1) it did not involve as-low-as-reasonably achievable planning or work controls,
(2) there was no overexposure,
(3) there was no substantial potential for an overexposure, and
(4) the ability to assess dose was not compromised.

Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. Specifically, the licensee noted that the workers had to change their work scope while accessing additional contaminated piping that contained a constant leakage of highly contaminated water (i.e., surveyed at 300,000 dpm/100cm2), and never stopped the job to determine if the radiological conditions they were exposed to were unknown or of high risk for contamination and possible unintended internal exposure.

Enforcement:

Violation: Technical Specification (TS) 5.4.1.a, states in part, written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, revision 2, appendix A, February 1978. Regulatory Guide 1.33, section 7.e., Procedures for Control of Radioactivity, recommends in part, adequate procedures for "Radiation Protection." Procedure RPP 02-105, RWP, revision 53, step 5.3.5, requires Stopping work whenever changes in the radiological conditions warrant such action or whenever compliance with the RWP requirements can NO longer be achieved.

Contrary to the above, on April 8, 2024, the licensee failed to follow licensee RP procedures.

Specifically, the licensee failed to follow Procedure RPP 02-105 when they did not stop when changes in the radiological conditions, (i.e., the constant dripping of highly contaminated water from the RHR piping) warranted such action and compliance with RWP requirements could no longer be achieved, by using a single set of protective clothing for a contamination area versus additional protective clothing and equipment for a high contamination condition.

This failure resulted in a personnel contamination event where a welder was found to have high levels of radioactive contamination on his shirt and his face.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.

Failure to Perform a Radiation Survey to Identify the Magnitude and Extent of Changing Radiological Conditions Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000482/2024002-03 Open/Closed

[H.1] -

Resources 71124.01 The inspectors identified a finding of very low safety significance (Green) and an associated non-cited violation of 10 CFR 20.1501(a) when the licensee failed to survey an area with changing radiological conditions. Specifically, on April 2, 2024, during activities associated with refueling outage 26, the licensee withdrew the incore detector thimbles and failed to survey the area above and around the entrance to the incore tunnel to identify the extent and magnitude of the changing radiation levels. As a result, workers in the high radiation area were not informed about elevated radiation levels as high as 240 millirem per hour at 30 centimeters from the incore tunnel entrance.

Type text here

Description:

On April 9, 2024, during refueling outage (RF) 26, NRC inspectors performed radiation surveys of the Wolf Creek reactor inside the bio-shield on the 2000-foot elevation of containment while the reactor was defueled. The entryway to the bio-shield was posted and barricaded as a high radiation area and contamination area. While performing a survey near the entrance to the incore tunnel, which was locked, enclosed, and posted with signage stating, "Grave Danger - Very High Radiation Area," the inspectors identified dose rates higher than expected based on the high radiation area briefing of radiological conditions within the bioshield and existing radiation protection (RP) survey maps. The inspectors identified that dose rates were over 200 millirem per hour at the ladder access entrance to the incore tunnel. The inspectors informed the licensee's RP staff about the elevated dose rates and the licensee performed confirmatory surveys to validate the inspectors' findings.

The licensee confirmed the dose rates were up to 240 millirem per hour at 30 centimeters from the incore tunnel ladder access and cover plate. These elevated dose rates were not previously recorded by the licensee on survey maps that were being used to brief workers entering the high radiation area. The previous surveys indicated that the highest dose rates in the same area were 12 millirem per hour at 30 centimeters, which were 20 times less than actually encountered. After additional discussions with the licensee, the inspectors determined that after the incore detector thimble tubes were withdrawn on April 2, 2024, no surveys were performed to assess the magnitude and extent of radiation levels in the area.

Subsequent to the withdrawal of the thimble tubes, scheduled refueling outage work activities continued in the area without workers being made knowledgeable of the increased dose rates until April 10th when the licensee performed the confirmatory surveys and updated the applicable survey maps of the area.

The inspectors requested a list of any work activity that had been performed in the area from the time of retracting the thimble tubes on April 2, 2024, until the time of the elevated dose rates discovery on April 9, 2024. The licensee provided information that confirmed work was performed in the area on April 5, 2024, and that workers would not have known the radiation levels had changed such that dose rates were 20 times higher than those briefed to them per the survey at the time.

Corrective Actions: On April 10, 2024, the licensee performed a survey at the incore tunnel entrance. The survey was documented, M-20240411-8, and the status boards were updated to reflect the current radiological conditions with dose rates as high as 240 millirem per hour at 30 centimeters from the incore tunnel entrance. The licensee then evaluated their RP program and process for deficiencies.

Corrective Action References: CRs 10032074 and 10032536

Performance Assessment:

Performance Deficiency: The licensee failed to perform an adequate survey to identify changing radiological conditions after withdrawing the incore thimbles, which resulted in workers not being made knowledgeable of the actual dose rates in the high radiation area that were up to 20 times higher than indicated on survey maps and briefed to the workers.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the program & process attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. Specifically, from April 2-10, 2024, work commenced in the high radiation area above and around the entrance to the incore tunnel without workers being made knowledgeable of the actual dose rates that were up to 20 times higher than indicated on survey maps and briefed to the workers, which challenged the licensee's ability to prevent unplanned dose.

Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix C, Occupational Radiation Safety SDP. The inspectors determined that the finding was of very low safety significance (i.e., Green) because:

(1) it did not involve as-low-as-reasonably achievable planning or work controls,
(2) there was no overexposure,
(3) there was no substantial potential for an overexposure, and
(4) the ability to assess dose was not compromised.

Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety.

Specifically, the licensee evaluated their program and process and determined that multiple procedures were deficient in information and requirements to evaluate changing radiological conditions. For example, procedures used for the incore thimble work failed to contain specific instructions to survey the area after withdrawal and insertion of the thimbles to ensure that actual radiological conditions were identified and documented to maintain knowledgeable workers in the field.

Enforcement:

Violation: Title 10 CFR 20.1501(a) requires, in part, that each licensee make or cause to be made surveys that

(1) may be necessary for the licensee to comply with the regulations in Part 20 and that surveys
(2) are reasonable under the circumstances to evaluate the magnitude and extent of radiation levels.

Contrary to the above, from April 2-10, 2024, the licensee failed to make or cause to be made surveys that complied with the regulations in Part 20 and were reasonable under the circumstances to evaluate the magnitude and extent of radiation levels in the area above and around the entrance to the incore tunnel. Specifically, the licensee failed to perform surveys after withdrawing the incore detector thimble tubes and evaluate the potential radiological hazards of the changing conditions when dose rates changed from 12 millirem per hour at 30 centimeters to 240 millirem per hour at 30 centimeters, which resulted in inaccurate survey maps being used to brief workers entering the high radiation area and those workers not being made knowledgeable of the actual radiological conditions.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.

Observation: Semiannual Trend 71152S The inspectors reviewed the licensees corrective action program, performance indicators, system health reports, and other documentation available to help identify performance trends that might indicate the existence of a more significant safety issue.

To verify that the licensee was taking corrective actions to address identified adverse trends that might indicate the existence of a more significant safety issue, the inspectors reviewed the corrective action program documentation associated with a potential adverse in performing and planning required post-maintenance testing following maintenance activities with a contributing cause associated with the cross-cutting aspect H.5, Work Management.

Selected examples of these events included:

  • NRC Integrated Inspection Report 05000482/2024001 documented non-cited violation (NCV) 2024001-02, Failure to Perform Post-Maintenance Testing Following Maintenance and Installation of the Bypass Reactor Trip Breaker, for the licensees failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability. Specifically, Work Order (WO) 18-445075-000 failed to provide appropriate instructions for safety-related bypass reactor trip breaker post-maintenance testing following maintenance and installation to verify the breaker was fully operable, by testing the technical specification required P-4 interlock that was later found to be inoperable due to incorrect wiring. The inspectors assigned a cross-cutting aspect of H-5, Work Management, because the licensee inappropriately planned the installation of the vendor overhauled reactor trip breakers in Mode 1 preventing the licensee from performing adequate post-maintenance testing to verify proper operation of the reactor trip breaker in the bypass location to ensure it was fully operable. The licensee-initiated Condition Reports 10031001 and 10031493.
  • The inspectors identified a minor finding and associated violation of Technical Specification 5.4.1.a for the licensees failure to implement Procedure AP 16E-002, Post Maintenance Testing, revision 21B, for containment cooler D motor and fan assembly replacement. Specifically, the licensee failed to plan post-maintenance testing to measure containment cooler D air flow capacity following the replacement of the motor and fan assembly. The inspectors determined the cross-cutting aspect H.5, Work Management, was applicable because the licensee failed to implement AP 16E-002 when planning, controlling, and executing work activities associated with the post-maintenance testing development of containment cooler Ds motor and fan assembly replacement during refueling outage 26. The licensee-initiated Condition Report 10032793 and a performed a satisfactory air flow capacity post-maintenance testing.
  • The licensee identified a minor finding and associated violation of Technical Specification 5.4.1.a for the licensees failure to perform required post-maintenance testing for auxiliary feedwater flow control valves ALHV0006, ALHV0008, and ALHV0012. Specifically, the licensee failed to perform Procedure STS AL-201C, Turbine Driven Auxiliary Feedwater System Inservice Valve Test, revision 13, in accordance with work orders: WO 53554, WO 53513, and WO 53369. The inspectors determined the cross-cutting aspect H.5, Work Management, was applicable due to the failure to coordinate work activities to address changing priorities across a whole spectrum of activities contributing to nuclear safety. Specifically, when the licensee changed to perform corrective maintenance for ALHV0006, ALHV0008, and ALHV0012 from online to the outage they failed to ensure the post-maintenance testing activities were also changed to the outage. The licensee-initiated Condition Report 10033418 and a performed Procedure STS AL-201C satisfactorily.
  • The inspectors reviewed Condition Report 10033122 and the associated performance assessment worksheet for the licensee failing to perform timed stroke testing of the air operated containment purge isolation valve GTHZ0008 following diagnostic testing.

The diagnostic testing procedure provides procedural guidance to remove and re-install the air-lines for GTHZ0008 in accordance with AP 29B-002, ASME Code Testing of Pumps and Valves, revision 12A, and WO 23-486310-002. The diagnostic testing was performed on April 14, 2024, during refueling outage 26 during the defueled window and the station entered Mode 6 on April 24, 2024. The licensees performance assessment worksheet concluded the operator mindset was to consider the need for post-maintenance testing when putting equipment back in service, not when taking it out of service. As a result, the need for the post-maintenance testing was missed. The inspectors reviewed the associated work orders: WO 23-486310-000, WO 23-486310-001, and WO 23-486310-002, and Technical Specification 3.9.4, Containment Penetrations. Technical Specification 3.9.4 states for the containment purge system, each penetration providing direct access from the containment atmosphere to the outside atmosphere either: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2. Capable of the being closed by an operable containment purge isolation valve. Work Order 23-486310-002 directed the licensee stroke GTHZ0008 in accordance with Procedure STS GP-001, Containment Purge Valves Actuation Test, revision 32. However, the work order was assigned a mode restraint of Mode 4, instead of a mode restraint of Mode 6. From this information the inspectors identified a minor finding and associated violation of Technical Specification 5.4.1.a for the licensees failure to performed required post-maintenance testing for GTHZ0008 prior to entering Mode 6. The inspectors determined the cross-cutting aspect H.5, Work Management, was applicable due to the failure to coordinate work activities to address changing priorities across whole spectrum of activities contributing to nuclear safety. Specifically, the licensee failed to assign the correct mode restraint for WO 23-486310-002 to ensure the post-maintenance testing for GTHZ0008 was completed prior to entering Mode 6 on April 24, 2024.

The inspectors concluded there was an adverse trend in a failure to perform and plan required post-maintenance testing following planned and corrective maintenance with a contributing cause associated with the cross-cutting aspect of H.5 Work Management.

Additionally, the inspectors noted the licensee also identified the adverse trend in a failure to perform and plan required post-maintenance testing. The licensee initiated CRs 10033639 and 10032794 for the adverse trend in post-maintenance testing activities. At the end of the inspection quarter, the licensee was still developing corrective actions to correct the post-maintenance testing adverse trend. The inspectors did not review any cross-cutting themes because none existed at the site.

EXIT MEETINGS AND DEBRIEFS

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

  • On April 23, 2024, the inspectors presented the RP inspection results to M. Boyce, Vice President, Engineering, and other members of the licensee staff.
  • On May 23, 2024, the inspectors presented the in-service inspection results to M. Boyce, Vice President, Engineering, and other members of the licensee staff.
  • On July 9, 2024, the inspectors presented the integrated inspection results to R. Bayer, General Manager, Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Calculations

AN 93-065

WCGS IPEEE High Winds

and Tornado Evaluation

71111.01

Calculations

CWS-SNP-

453C

Revised SNP Setpoints

03/01/1984

71111.01

Corrective

Action

Documents

Condition

Reports

2000-1528, 10015262

71111.01

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10033969, 10034320

71111.01

Drawings

M-12BG03

Piping and Instrumentation

Diagram Chemical and

Volume Control System

71111.01

Drawings

M-12BG05

Piping and Instrumentation

Diagram Chemical and

Volume Control System

71111.01

Miscellaneous

M-10BG

System Description Chemical

and Volume Control System

71111.01

Miscellaneous

WCRE-03

Wolf Creek Tank Document

71111.01

Miscellaneous

WCRE-34

Fourth 10-Year Interval

Inservice Testing Basis

Document

71111.01

Procedures

AI 14-006

Severe Weather

71111.01

Procedures

ALR 00-047D

RWST Lev LOLO 1 Auto XFR

10B

71111.01

Procedures

ALR 00-047E

RWST Lev HILO

71111.01

Procedures

EMG E-0

Reactor Trip or Safety

Injection

71111.01

Procedures

EMG ES-02

Reactor Trip Response

71111.01

Procedures

EMG ES-04

EMG ES-04, Natural

Circulation Cooldown

71111.01

Procedures

OFN BG-009

Emergency Boration

71111.01

Procedures

OFN SG-003

Natural Events

71111.04

Corrective

Action

Documents

Condition

Reports

10031465, 10031524,

10031582, 10031680,

10031710, 10031715,

10031745, 10031800,

10031854, 10031864,

10031870, 10031882,

10032073, 10032095,

10032099, 10032106,

10032118, 10032183,

10032221, 10032258,

10032275, 10032576,

10032649, 10032772

Type txt here

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031367, 10031952,

10032260

71111.04

Drawings

M-12BB01

Piping and Instrumentation

Diagram Reactor Coolant

System

71111.04

Drawings

M-12BG03

Piping and Instrumentation

Diagram Chemical and

Volume Control System

71111.04

Drawings

M-12BN01

Piping and Instrumentation

Diagram Borated Refueling

Water Storage Tank

71111.04

Drawings

M-12EJ01

Piping and Instrumentation

Diagram Residual Heat

Removal System

71111.04

Drawings

M-12EM01

Piping and Instrumentation

Diagram High Pressure

Coolant Injection System

71111.04

Drawings

M-12EP01

Piping and Instrumentation

Diagram Accumulator Safety

Injection

71111.04

Miscellaneous

E-1F9905

Fire Hazard Analysis

71111.04

Miscellaneous

E-1F9910

Post Fire Safe Shutdown Area

Analysis

71111.04

Miscellaneous

E-1F9915

Design Basis Document for

Procedure OFN RP-017

71111.04

Miscellaneous

WCRE-34

Fourth 10-Year Interval

Inservice Testing Basis

Document

71111.04

Procedures

AP 14A-003

Scaffold Construction

26A

71111.04

Procedures

AP 23L-002

Heat Exchanger Program

71111.04

Procedures

GEN 00-008

RCS Level Less Than Reactor

Vessel Flange Operations

71111.04

Procedures

OFN BB-031

Shutdown LOCA

71111.04

Procedures

OFN EJ-015

Loss of RHR Cooling

71111.04

Procedures

OFN EJ-040

CL Recirc during Mode 3, with

Accumulators Isolated, Mode

4, 5, or 6

71111.04

Procedures

OFN RP-017

Control Room Evacuation

71111.04

Procedures

OFN RP-017A

Hot Standby to Cold

Shutdown form Outside the

Control Room Due to Fire

71111.04

Procedures

STN PE-038

Containment Cooler

Performance Test

71111.04

Work Orders

WO

242, 55856, 55907, 56780,

56910, 56991, 57658,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

20-462334-000, 21-475554-

000, 23-483955-000

71111.05

Corrective

Action

Documents

Condition

Reports

10031116, 10031234,

10031523, 10031878,

10032097

71111.05

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10032199, 10032254,

10032255

71111.05

Miscellaneous

WCRE-35

Boundary Matrix

71111.05

Procedures

AP 10-103

Fire Protection Impairment

Control

71111.05

Procedures

AP 10-104

Breach Authorization

71111.05

Work Orders

WO

56908

71111.07A

Calculations

EG-08-W

Minimum Wall Thickness in

Cooling Water Heat

Exchangers EEG01A and

EEG01B

71111.07A

Calculations

EG-09-W

Tube Plugging for CCW Heat

Exchangers

71111.07A

Corrective

Action

Documents

Condition

Reports

10031516, 10031578,

10031579, 10031581,

10031582, 10031726,

10031854, 10032260,

10032870

71111.07A

Drawings

M-1HX001

Heat Exchanger Tube Sheet

Map Component Cooling

Water Heat Exchanger "A"

(North End) EEG01A

71111.07A

Drawings

M-1HX001

Heat Exchanger Tube Sheet

Map Component Cooling

Water Heat Exchanger "B"

(South End) EEG01AB

71111.07A

Procedures

STN PE-033

CCW Heat Exchanger

Performance Test

71111.07A

Work Orders

WO

23-484909-000

04/11/2024

71111.08P

Corrective

Action

Documents

Condition

Reports

10018380, 10018382,

10018387, 10019129,

10019132, 10019603,

10020507, 10020515,

10020517, 10020493,

10020491, 10020492,

10020507, 10020512,

10020515, 10020517,

10029772, 10030434,

10030796, 10031467,

10031482, 10031486,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

10031679, 10031706,

10031862, 10031864,

10031896, 10031957,

10031999, 10032067,

10032127, 10032172,

10032298, 10032330,

10032370, 10032379

71111.08P

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031259, 10031553,

10031924, 10031947,

10033822, 10033823

71111.08P

Drawings

M-12EM01

Piping & Instrumentation

Diagram High Pressure

Coolant Injection System

71111.08P

Drawings

M-13EJ01

Piping Isometric Residual

Heat Removal System

Auxiliary Bldg. "A" Train

71111.08P

Drawings

M-13EM07

Small Piping Isometric High

Pressure Coolant Injection

System - Aux. Bldg.

71111.08P

Drawings

M-703-00023

SHUPPS Lower Internals

Assembly

71111.08P

Drawings

M-703-00024

SHUPPS Upper Internals

Assembly

71111.08P

Drawings

M-703-00059

Loop Lower Radial Support

Clevis Insert Gaging and

Assembly

71111.08P

Miscellaneous

AI 16F-001

Evaluation of Boric Acid

Leakage

71111.08P

Miscellaneous

AI 16F-002

Boric Acid Leakage

Management

71111.08P

Miscellaneous

AP 16A-003

ASME Section XI

Repair/Replacement Program

20B

71111.08P

Miscellaneous

AP 16F-001

Boric Acid Corrosion Control

Program

71111.08P

Miscellaneous

I-ENG-023

Steam Generator Data

Analysis Guidelines

71111.08P

Miscellaneous

INR-WC-

1R26-24-002

Remote Visual Examination

Indication Notification Report

04/12/2024

71111.08P

Miscellaneous

M-703-00207

W02

Design Specifications for

Nuclear Reactor Internals

11/25/2003

71111.08P

Miscellaneous

WCRE-30

Inservice Inspection Program

Plan Wolf Creek Generation

Station Interval 4

71111.08P

Miscellaneous

WR 02070-90

Engineering Disposition

04/17/1990

71111.08P

NDE Reports

5167

Magnetic Particle

Examination, WBU-6A

05/07/2024

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.08P

NDE Reports

5168

Magnetic Particle

Examination, BW-4

05/07/2024

71111.08P

NDE Reports

STS PE-040A

Reactor Coolant System Test

2/8/2022

71111.08P

NDE Reports

STS PE-040E

RPV Head Bare Metal

Inspection

05/02/2024

71111.08P

NDE Reports

STS PE-040E

RPV Head Bare Metal

Inspection

11/16/2022

71111.08P

NDE Reports

STS PE-040H

RPV Head NDE Examination

11/16/2022

71111.08P

Procedures

54-ISI-364-

009

Remote Underwater Visual

Examination of Reactor

Pressure Vessels, Vessel

Internals, and Components in

Pressurized Water Reactors in

Accordance with Section XI

2/22/2018

71111.08P

Procedures

54-ISI-364-

009

Remote Underwater Visual

Examination of Reactor

Pressure Vessels, Vessel

Internals, and Components in

Pressurized Water Reactors in

Accordance with Section XI.

71111.08P

Procedures

CWD-1

Control of Welding

Documentation

71111.08P

Procedures

GWS-ASME

ASME General Welding

Standard

71111.08P

Procedures

LMT-08-PDI-

UT-1

Ultrasonic Examination of

Ferritic Piping Welds

71111.08P

Procedures

LMT-08-PDI-

UT-2

Ultrasonic Examination of

Austenitic Piping Welds

71111.08P

Procedures

LMT-08-PDI-

UT-5

Straight Beam Ultrasonic

Examination of Bolts and

Studs

71111.08P

Procedures

LMT-08-PDI-

UT-6

Ultrasonic Examination of

Reactor Pressure Vessel

Closure Head Welds and

Adjacent Base Metal

71111.08P

Procedures

LMT-21-

PAUT-028

Manual Phased Array

Ultrasonic Examination of

Pressure Retaining Welds in

Control Rod (CRD) Housings

71111.08P

Procedures

QCP-20-541

VT-3 Visual Examination

71111.08P

Procedures

STS PE-040E

RPV Head Visual Examination

71111.08P

Work Orders

WO

16-418193-000, 17-431456-

001, 19-450006-000,

21-474032-056, 21-474032-

066, 21-474032-067,

2-482436-002, 22-482488-

000, 12003, 12008, 12011,

2013, 12015, 12017, 12346,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2348, 55017, 55020

71111.11Q

Corrective

Action

Documents

Condition

Report

10033371

71111.11Q

Procedures

GEN 00-003

Hot Standby to Minimum Load

111

71111.11Q

Procedures

RXE 01-002

Reload Low Power Physics

Testing

71111.12

Calculations

KA-03-W

KA System Back-up Nitrogen

Accumulators Capacity

Calculation

71111.12

Corrective

Action

Documents

Condition

Reports

33653, 33654, 33758, 121822,

23103, 137915, 142204,

10007665, 10012448,

10012555, 10030624,

10030630, 10030361,

10030650, 10030667,

10030732, 10030733,

10030734, 10030736,

10030739, 10030769,

10032166, 10032356,

10032400, 10033032

71111.12

Drawings

M-11EF01

System Flow Diagram

Essential Service Water

71111.12

Drawings

M-12EF02

Piping and Instrumentation

Diagram Essential Service

Water System

71111.12

Drawings

M-12GN01

Piping and Instrumentation

Diagram Containment Cooling

System

71111.12

Drawings

M-12KA05

Piping and Instrumentation

Diagram Compressed Air

System

71111.12

Engineering

Changes

CCP 07378

Containment Cooler Fusible

Link Equivalency Evaluation

71111.12

Engineering

Changes

DCP 15241

Spent Fuel Pool Alternate

Cooling Modification

71111.12

Engineering

Changes

DRE 20456

AV1 Positioner Gauge Block

Removal

71111.12

Miscellaneous

M-10GN

System Description for

Containment Cooling System

71111.12

Miscellaneous

M-620

Design Specification for

Containment Coolers for Wolf

Creek Nuclear Operating

Corporation (WCNOC)

71111.12

Procedures

AP 16-003

Master Lubrication List and

Control of Lubricants

71111.12

Procedures

AP 23L-002

Heat Exchanger Program

71111.12

Procedures

AP 26C-004

Operability Determination and

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Functionality Assessment

71111.12

Procedures

BD OFN NB-

234

Loss of All AC Power -

Shutdown Conditions

71111.12

Procedures

INC C-0010

7300 Loop P/S Card (NLP1)

3B

71111.12

Procedures

INC S-0020

Air Operated Valve (AOV)

Diagnostic Testing

71111.12

Procedures

OFN EC-046

Fuel Pool Cooling and

Cleanup Malfunctions

71111.12

Procedures

OFN NB-034

Loss of All AC Power -

Shutdown Conditions

71111.12

Procedures

STN EF-022B

ESW Train B Post-LOCA Flow

Balance

71111.12

Procedures

STN PE-037A

ESW Train A Heat Exchanger

Flow and DP Trending

2A

71111.12

Procedures

STN PE-037B

ESW Train B Heat Exchanger

Flow and DP Trending

71111.12

Procedures

STS EF-925A

Containment Coolers Flow

Rate (Upon Safety Injection)

Verification - Train A

71111.12

Procedures

STS EF-925A

Containment Coolers Flow

Rate (Upon Safety Injection)

Verification - Train A

71111.12

Procedures

STS EF-925B

Containment Coolers Flow

Rate (Upon Safety Injection)

Verification - Train B

71111.12

Procedures

STS KA-010

Accumulator Inservice Check

Valve Test

71111.12

Procedures

SYS EC-202

Staging Alternate Spent Fuel

Pool Cooling

71111.12

Work Orders

WO

13326, 16866, 20453, 22872,

50424, 20-459056-000,

17-432437-006, 18-441848-

004, 20-464226-000,

20-467458-000, 21-471451-

000, 21-472154-000,

21-473086-004, 21-473493-

000, 21-474438-000,

2-477036-000, 22-480069-

000, 22-481429-000,

23-483713-000, 23-483892-

000, 23-483899-000,

23-484530-000, 23-488240-

000

71111.13

Corrective

Action

Documents

Condition

Reports

10031603, 10031604,

10033200, 10033869,

10033938, 10034274

71111.13

Drawings

25-C-

KG1202

Site Plan

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.13

Drawings

E-13EF04A

Schematic Diagram ESW

From Component Cooling

Water Heat Exch. ISO Valve

EFHV0060

71111.13

Drawings

S-81

Ultimate Heat Sink Plan

G

71111.13

Miscellaneous

Specification Number C-302

71111.13

Procedures

OFN NB-030

Loss of AC Emergency Bus

NB01 (NB02)

71111.13

Procedures

STN FC-002

Aux Feedwater Turbine

Overspeed Test

34A

71111.13

Procedures

STN RP-002H

ESW TRN B To/From CCW

HX B ISO Switches

71111.13

Procedures

STS IC-805A

Channel Calibration of NB01

Grid Degraded Voltage, Time

Delay Trip

15A

71111.13

Procedures

TMP 10-035

Dredging the UHS Channel

71111.13

Work Orders

WO

17123, 61319, 64522, 66805

71111.15

Calculations

KA-03-W

KA System Back-up Nitrogen

Accumulators Capacity

Calculation

71111.15

Corrective

Action

Documents

Condition

Reports

33653, 33654, 33758,

10005547, 10029678,

10030624, 10030630,

10030361, 10030650,

10030667, 10030732,

10030733, 10030734,

10030736, 10030739,

10031933, 10032433,

10032656, 10033139,

10033418, 2008-05818

71111.15

Corrective

Action

Documents

Resulting from

Inspection

Condition

Report

10034767

71111.15

Drawings

M-12EF02

Piping and Instrumentation

Diagram Essential Service

Water System

71111.15

Drawings

M-12KA05

Piping and Instrumentation

Diagram Compressed Air

System

71111.15

Miscellaneous

M-018-00309

Instruction Manual for

Emergency Diesel Generator

System

W141

71111.15

Miscellaneous

M-721-00093

Instruction Manual for

Charging/Safety Injection

Pump

W50

71111.15

Operability

KA-11-001

Operability Evaluation

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

71111.15

Procedures

AP 26C-004

Operability Determination and

Functionality Assessment

71111.15

Procedures

CKL KU-120

SBO DG Component

Checklist

71111.15

Procedures

EMG C-0

Loss of All AC Power

71111.15

Procedures

QCP-20-502

Magnetic Particle Examination

AC/DC Yoke and AC Coil

Techniques

71111.15

Procedures

STN KU-001A

SBO DG to NB01 Functional

Test

71111.15

Procedures

STS KA-010

N2 Accumulator Inservice

Check Valve Test

71111.15

Procedures

STS KU-121

Energizing NB01 from Station

Blackout Diesel Generators

71111.15

Work Orders

WO

13326, 22872, 40594, 50424,

216, 58244, 08-312917-

005, 20-459655-000, 21-

471249-000, 22-481429-000,

23-484530-000, 23-487665-

000, 23-488240-000

71111.18

Calculations

XX-E-006

AC System Analysis

71111.18

Corrective

Action

Documents

Condition

Reports

10028675, 10028767,

10029120, 10030207,

10030607, 10030882,

10031049, 10031320,

10031321, 10031341,

10031502, 10031518,

10031586, 10031664,

10031897, 10031898,

10032140, 10032251,

10032267, 10032341,

10032395, 10032407,

10032444

71111.18

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031379, 10034770

71111.18

Drawings

M-12BB04

Piping and Instrumentation

Diagram Reactor Coolant

System

71111.18

Drawings

M-705-00020

Bottom Mounted Instrument

Thimble Guide

W02

71111.18

Drawings

M-705-00024

Bottom Mounted Instrument

Thimble Guide

W08

71111.18

Drawings

M-705-00026

Bottom Mounted Instrument

Thimble Guide

W07

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.18

Drawings

M-705-00029

Bottom Mounted Instrument

Thimble Guide

W01

71111.18

Drawings

M-764-00316

Bottom Mounted Instrument

Thimble Guide

B2

71111.18

Engineering

Changes

CP 012331

Seal Table Maintenance

Fitting Assembly Replacement

0, 1, 2

71111.18

Engineering

Changes

DCP 01500

Start-Up Transformer

(XMR01) Replacement

71111.18

Engineering

Changes

DECP 020771

Remove Flux Thimble at

Rector Location L-8 from

Service

71111.18

Miscellaneous

E-10NF(Q)

Load Shedding and

Emergency Load Sequencing

71111.18

Miscellaneous

M-705-00032

Deep Bore Seal Table

Maintenance Fitting Assembly

Installation at Wolf Creek

W03

71111.18

Miscellaneous

TR-94-0015

WCNOC Cycle 27 Core

Operating Limits Report

(COLR)

71111.18

Miscellaneous

WCAP-16676-

NP

Analysis Update for the

Inadvertent Loading Event

03/00/2009

71111.18

Miscellaneous

WCRE-23

Inservice Inspection

Classification Basis Document

71111.18

Procedures

AI 22D-003

Outage Scope Identification,

Control and Risk

Determination

71111.18

Procedures

AP 15D-008

Wolf Creek Cyber Security

Program

71111.18

Procedures

AP 16A-003

ASME Section XI

Repair/Replacement Program

71111.18

Procedures

AP 16E-002

Post Maintenance Testing

Development

21B

71111.18

Procedures

AP 29A-004

ASME Section XI System

Pressure Testing

2A

71111.18

Procedures

INC S-0607

Incore Detector Thimble

Insertion

71111.18

Procedures

STS KJ-001B

Integrated D/G and

Safeguards Actuation Test -

Train B

71111.18

Procedures

STS PE-040A

Reactor Coolant System

Pressure Test

16A

71111.18

Work Orders

WO

2663, 55830, 57623, 57655,

57757, 58130, 58270,

23-484977-002

71111.20

Corrective

Action

Documents

Condition

Reports

101466, 10006003, 10015377,

10019243, 10028254,

10030261, 10030278,

10030526, 10030881,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

10031056, 10031112,

10031126, 10031256,

10031263, 10031266,

10031428, 10031430,

10031467, 10031518,

10031519, 10031537,

10031702, 10031704,

10031760, 10031761,

10031784, 10031813,

10031824, 10031846,

10032104, 10032161,

10033063, 10033065,

10033088, 10033655

71111.20

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031377, 10031960,

10033154, 10033155,

10033156, 10033157,

10034768, 10034769

71111.20

Procedures

AI 15C-006

Management Oversight

Requirements for Infrequently

Performed and Potentially

Degrading Evolutions

71111.20

Procedures

AP 14-001

Control of Heavy Loads,

Lifting, and Rigging

6A

71111.20

Procedures

AP 16F-001

Boric Acid Corrosion Control

Program

71111.20

Procedures

FHP 02-007A

Reactor Vessel Closure Head

Removal

71111.20

Procedures

FHP 02-016

Reactor Vessel Lower

Internals Removal and

Installation

71111.20

Procedures

GEN 00-008

RCS Level Less Than Reactor

Vessel Flange Operations

71111.20

Procedures

MGM MOOP-

Relief Valve Bench Testing

26A

71111.20

Procedures

STN EJ-002

Containment Inspection

71111.20

Procedures

STN PE-040D

RCS Pressure Boundary

Integrity Walkdown

71111.20

Procedures

STS MT-070

ASME Code Testing of

Safety/Relief Valves

71111.20

Work Orders

WO

33719, 55472, 55705, 60885,

20-461819-000, 20-461819-

001, 20-461819-003, 20-

2020-003, 21-474028-000,

21-474028-001, 21-474028-

003, 21-474101-000,

21-474101-001, 21-474101-

003, 23-487552-000,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

23-487553-000

71111.24

Corrective

Action

Documents

Condition

Reports

73421, 101466, 10008190,

10008191, 10015380,

10020251, 10021293,

10028066, 10029827,

10029828, 10030112,

10030189, 10030193,

10030525, 10031127,

10031187, 10031343,

10031400, 10031401,

10031722, 10031805,

10031806, 10031895,

10032019, 10032099,

10032101, 10032207,

10032223, 10032225,

10032226, 10032257,

10032276, 10032408,

10032433, 10032475,

10032477, 10032534,

10032553, 10032570,

10032656, 10032677,

10032730, 10032772,

10032848, 10032963,

10033001, 10033066,

10033139, 10033145,

10033147, 10033149,

10033180, 10033366,

10033857, 10034200

71111.24

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031379, 10032272,

10032492, 10032793,

10033210, 10033213

71111.24

Drawings

E-025-00007

sheet 236

RHR A to SIS Hot Leg Recirc

Loops 2 and 3 ISO

W14

71111.24

Drawings

M-12BB03

Piping and Instrumentation

Diagram Reactor Coolant

Pump

71111.24

Drawings

M-12EF01

Piping and Instrumentation

Diagram Essential Service

Water System

71111.24

Drawings

M-12EF02

Piping and Instrumentation

Diagram Essential Service

Water System

71111.24

Drawings

M-12EJ01

Piping and Instrumentation

Diagram Residual Heat

Removal System

71111.24

Drawings

M-724-00595

Nozzle Type Relief Valve

W03

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.24

Drawings

M-K2EF01

Piping and Instrumentation

Diagram Essential Service

Water System

71111.24

Engineering

Changes

WCNO#PES-

00069-REPT-

2

Wolf Creek Unit 1 STRIDE 23-

Risk Evaluation

71111.24

Miscellaneous

STRIDE 21-01

Wolf Creek Integrated D/G

and Safeguards Actuation

Testing

71111.24

Miscellaneous

WCOP-02

Inservice Testing Program for

Pumps, Valves, and Snubbers

71111.24

Miscellaneous

WCOP-02

Inservice Testing Program for

Pumps, Valves, and Snubbers

71111.24

Miscellaneous

WCRE-34

Fourth 10-Year Interval

Inservice Testing Basis

Document

71111.24

Procedures

AP 16E-002

Post Maintenance Testing

Development

21B

71111.24

Procedures

AP 21D-004

Control of Containment

Penetrations during Shutdown

Operations

11B

71111.24

Procedures

AP 29B-002

ASME Code Testing of Pumps

and Valves

2A

71111.24

Procedures

AP 29E-001

Program Plan for Containment

Leakage Measurement

17A

71111.24

Procedures

AP 29G-001

RCS Unidentified Leak Rate

Monitoring Program

71111.24

Procedures

E-13GN02A

Schematic Diagrams

Containment Cooler Fans B

and D

1B

71111.24

Procedures

GEN 00-006

Hot Standby to Gold

Shutdown

106

71111.24

Procedures

MGE LT-100

Llmitorque Valve Operator

General Notes and Details

71111.24

Procedures

STN EJ-202

RHR System Valve Test

71111.24

Procedures

STS AE-209A

Main Feed Reg Valve Bypass

Valve Inservice Valve Test

Train A

71111.24

Procedures

STS AE-209B

Main Feed Reg Valve Bypass

Inservice Valve Test Train B

71111.24

Procedures

STS BB-006

RCS Water Inventory Balance

Using the NPIS Computer

71111.24

Procedures

STS CV-106

Inservice Testing Check Valve

Condition Monitoring for

EFV0476, 0478, 0482, 0484

71111.24

Procedures

STS GN-001

CTMT Cooling Fans

Operability Test

71111.24

Procedures

STS KJ-001A

Integrated D/G and

73A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Safeguards Actuation Test -

Train A

71111.24

Procedures

STS KJ-001B

Integrated D/G and

Safeguards Actuation Test -

Train B

71111.24

Procedures

STS KJ-011B

DG NE02 24 Hour Run

71111.24

Procedures

STS MT-008

S/G Spring Loaded Safety

Valve Settings

27D

71111.24

Procedures

STS MT-070

ASME Code Testing of

Safety/Relief Valves

71111.24

Procedures

STS PE-122

LLRT Valve Lineup for

Penetration 22

71111.24

Procedures

SYS KJ-124

Post Maintenance Run of

Emergency Diesel Generator

B

71111.24

Work Orders

WO

2362, 12703, 15900, 20864,

23060, 24808, 44349, 46438,

251, 56102, 56910, 57458,

57647, 57695, 59503, 60540,

60580, 60601, 61166, 61169,

14-395986-006, 15-399425-

003, 17-425266-005, 17-

25266-006, 17-425266-007,

17-425266-008, 20-461819-

000, 20-461819-001,

20-461819-003, 20-462020-

003, 21-474028-000,

21-474028-001, 21-474028-

003, 21-474101-000,

21-474101-001, 21-474101-

003, 23-483960-000,

23-485386-000, 23-485745-

000, 23-485746-000,

23-485829-002, 23-485897-

000, 23-487424-000,

23-487552-000, 23-487553-

000, 23-487813-000

71114.06

Corrective

Action

Documents

Condition

Reports

10034406, 10034408,

10034410, 10034413,

10034417, 10034421,

10034422, 10034426,

10034430, 10034432,

10034433, 10034434,

10034435, 10034437,

10034438, 10034444,

10034447, 10034450,

10034452, 10034454,

10034455, 10034456,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

10034471, 10034490

71114.06

Corrective

Action

Documents

Resulting from

Inspection

Condition

Report

10034519

71114.06

Procedures

ALR 00-123A

MFP B Trip

71114.06

Procedures

EMG E-0

Reactor Trip or Safety

Injection

71114.06

Procedures

OFN NB-030

Loss of AC Emergency Bus

NB01 (NB02)

71124.01

ALARA Plans

RWP 240061

Fuel Building Transfer Canal

Entry

10/30/2023

71124.01

ALARA Plans

RWP 244420

Scaffolding Activities

11/01/12023

71124.01

ALARA Plans

RWP 246020

Reactor Vessel Head

Preparation

10/02/2023

71124.01

Corrective

Action

Documents

Condition

Reports

10027419, 10027420,

10027133, 10028178,

10028180, 10028295,

10030172, 10030174,

10030175

71124.01

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10031817, 10031822,

10031829, 10031843,

10031852, 10032026,

10032028, 10032034,

10032074, 10032152,

10032215, 10032250,

10032533, 10032535,

10032536, 10032537,

10032540

71124.01

Procedures

AP 25A-001

Radiation Protection Manual

20A

71124.01

Procedures

AP 25A-100

Containment Entry

19A

71124.01

Procedures

AP 25A-200

Access to Locked High or

Very High Radiation Areas

29A

71124.01

Procedures

AP 25A-401

ALARA Program

71124.01

Procedures

AP 25A-700

Use of Temporary Shielding

19C

71124.01

Procedures

AP 25B-100

Radiation Worker Guidelines

56A

71124.01

Procedures

AP 25D-001

Self-Assessment Process

71124.01

Procedures

AP 26A-009

NRC Interface and Inspection

Guidance

71124.01

Procedures

INC S-0606

Incore Detector Thimble

Withdrawal

71124.01

Procedures

RPP 02-105

RWP

71124.01

Procedures

RPP 02-210

Radiation Survey Methods

71124.01

Procedures

RPP 02-215

Posting of Radiological

Controlled Areas

36A

71124.01

Procedures

RPP 02-405

RCA Access Control

71124.01

Procedures

RPP 02-510

Discrete Radioactive Particle

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Contamination Control

71124.01

Procedures

RPP 02-515

Release of Radioactive

Material from the RCA

71124.01

Radiation

Surveys

M-20190919-

RadWaste General Floor Area

Routine

09/19/2029

71124.01

Radiation

Surveys

M-20240330-

I/S Bioshield Post-Peroxide

Survey B/C Loop down post

03/30/2024

71124.01

Radiation

Surveys

M-20240402-

Pulling Incore Thimble Tubes

04/01/2024

71124.01

Radiation

Surveys

M-20240403-

Reactor Head Scaffold Survey

04/03/2024

71124.01

Radiation

Surveys

M-20240404-

RadWaste East Title:

Thursday Weekly

04/04/2024

71124.01

Radiation

Surveys

M-20240404-

RB2047C RV Head Stand -

Bare Metal Inspection of RV

Head

04/04/2024

71124.01

Radiation

Surveys

M-20240407-

Socket weld prep work on

EJV0169 and EJV0007

04/07/2024

71124.01

Radiation

Surveys

M-20240407-5

47' CTMT After Draindown

04/07/2024

71124.01

Radiation

Surveys

M-20240407-7

1974 RHR A Drain line

removal EJV-Title: 0007, EJV-

0169

04/07/2024

71124.01

Radiation

Surveys

M-20240407-8

2000' CTMT Seal Table -

Thimble Retraction

04/07/2024

71124.01

Radiation

Surveys

M-20240408-

Weekly Survey 2000'

Containment

04/08/2024

71124.01

Radiation

Surveys

M-20240408-

Daily 2000' RadWaste

04/08/2024

71124.01

Radiation

Surveys

M-20240408-

PCE#818

04/08/2024

71124.01

Radiation

Surveys

M-20240408-

Contamination survey of "A"

RHR Pump Room

04/08/2024

71124.01

Radiation

Surveys

M-20240409-2

Weld "A" RHR Pump EJV-

0007 and EJV-0169

04/08/2024

71124.01

Radiation

Surveys

M-20240409-

RHR "A " Pre-Job Welding

Walkdown

04/09/2024

71124.01

Radiation

Surveys

M-20240409-9

26' Containment Weekly

Survey

04/09/2024

71124.01

Radiation

Surveys

M-20240410-

Skimmers labeled with

Radioactive Material sticker

04/10/2024

71124.01

Radiation

Surveys

M-20240411-8

2000' I/S Bio - Dose Rate

Verification at VHRA Incore

Tunnel Boundary

04/10/2024

71124.01

Radiation

Surveys

M-20240416-

2000' BCHV-8160 Letdown

04/16/2024

71124.01

Radiation

Work Permits

RWP 230036

Containment access during

plant modes 1, 2, 3, 4, & 5 for

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

(RWPs)

maintenance functions

71124.01

Radiation

Work Permits

(RWPs)

RWP 230120

LHRA Waste processing

activities requiring High Risk

Radiation Protection (RP)

Supervisory Oversight

71124.01

Radiation

Work Permits

(RWPs)

RWP 230610

Prepare Dry Storage

Container (DSC) and Transfer

Cask (TC) for fuel loading,

load DSC with Fuel, relocate

DSC to Cask Washdown Pit

(CWP), decontaminate

DSC/TC, close DSC, move

DSC/TC to Fuel Building truck

bay

71124.01

Radiation

Work Permits

(RWPs)

RWP 242001

Welding Activities

71124.01

Self-

Assessments

Audit Report

No: 24-01-

RP/PC

QUALITY ASSURANCE

AUDIT REPORT

Radiological Protection and

Process Control

2/28/2024

71124.01

Work Orders

23-483995-

000

Perform INC S-0606 In-core

Detector Thimble Withdrawal

04/02/2024

71124.03

Corrective

Action

Documents

Condition

Reports

10024319, 10024625,

10025705, 10025717,

10026482, 10026816,

10027295, 10028605,

10029010, 10030210,

10020326, 10030237

71124.03

Corrective

Action

Documents

Resulting from

Inspection

Condition

Reports

10030237, 10031852,

10032026, 10032028,

10032034

71124.03

Drawings

A-KAT-12

Piping and Instrumentation

Diagram: Mechanical HVAC

Plans Sections and Details

71124.03

Drawings

M-12GK01

Piping and Instrumentation

Diagram: Control Building

HVAC

71124.03

Drawings

M-12GK03

Piping and Instrumentation

Diagram: Control Building

HVAC

71124.03

Miscellaneous

Air Sample Logs: January 1,

23, to March 14, 2024

71124.03

Miscellaneous

Updated Safety Analysis

Report (USAR), Chapter 9.4 -

Air Conditioning, Heating,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Cooling, and Ventilation

71124.03

Miscellaneous

USAR, Chapter12.0 -

Radiation Protection

71124.03

Miscellaneous

System Health Report

(7/1/2023 - 12/31/2023): Fuel

Building HVAC system

04/11/2024

71124.03

Miscellaneous

2-480447-

000

Charcoal Adsorbent In-Place

Leak Test Safety Related

Units - FGK02B

07/06/2023

71124.03

Miscellaneous

2-481189-

000

Charcoal Adsorbent Sampling

for Nuclear Safety Related

Units - FGK02A

2/23/2023

71124.03

Miscellaneous

2-482265-

000

HEPA Filter In-Place Leak

Test Safety Related Units -

FGK01A

06/19/2023

71124.03

Miscellaneous

2-482268-

000

Charcoal Adsorbent Sampling

for Nuclear Safety Related

Units - FGK01A

06/19/2023

71124.03

Miscellaneous

23-487062-

000

HEPA Filter In-Place Leak

Test Safety Related Units -

FGK02A

07/19/2023

71124.03

Miscellaneous

AIF 10-001-02

SCBA Inspections from

November 4, 2022, to

February 5, 2024

2/05/2024

71124.03

Miscellaneous

GT 1245302

Self-Contained Breathing

Apparatus Training

71124.03

Procedures

AI 10-004

Air Fill Station Operation

4A

71124.03

Procedures

AI 14-009

Industrial Respiratory

Protection Program

71124.03

Procedures

AP 25B-600

Respiratory Protection

Program at Wolf Creek

71124.03

Procedures

RPP 03-210

Internal Exposure Calculations

and Evaluations

17D

71124.03

Procedures

RPP 03-310

Respiratory Protection

Equipment

71124.03

Procedures

RPP 05-201

Eberline RAS-1 Operation for

Tritium Air Sampling

71124.03

Procedures

RPP 05-205

AMS-4 Operation

71124.03

Procedures

RPP 05-920

Use of Vacuum Cleaners and

Portable HEPA Ventilation

Units in the RCA

7A

71124.03

Procedures

STN PE-004

Charcoal Adsorber In-Place

Leak Test Non-Safety Related

Units

71124.03

Procedures

STS PE-006A

Train A Charcoal Adsorber In-

Place Leak Test Safety

Related Units

71124.03

Procedures

SYS GK-121

Control Building HVAC

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Operations

71124.03

Procedures

SYS GK-123

Control Building A/C Units

Startup and Shutdown

71124.03

Procedures

SYS VT-100

Technical Support Center

HVAC Startup and Shutdown

71124.03

Radiation

Surveys

AS 24-0060

Airborne Radioactivity Record:

26' Fuel Building

2/27/2024

71124.03

Radiation

Surveys

AS 24-0064

Airborne Radioactivity Record:

26' Fuel Building

2/27/2024

71124.03

Radiation

Surveys

M-20240409-

S/G B & C Primary Dose Rate

& Smear Survey

04/09/2024

71124.03

Radiation

Surveys

M-20240409-6

2000' CTMT, S/G "A" & "D"

Routine Survey

04/09/2024

71124.03

Radiation

Work Permits

(RWPs)

RWP 243200

Radiation Protection Primary

and Secondary Steam

Generator Rover Coverage

71124.08

Procedures

RPP 07-111

Handling Cartridge Filters

71124.08

Procedures

RPP 07-123

Preparation and Shipment of

Radioactive Waste and

Material

9D

71124.08

Shipping

Records

24R09

UN2912, Radioactive

materials, low specific activity

(LSA-I), 7, Fissile Excepted,

dry active waste

04/10/2024

71151

Procedures

DB-EMG ES-

Transfer to Cold Leg

Recirculation

71151

Procedures

EMG ES-12

Transfer to Cold Leg

Recirculation

71151

Procedures

WCNOC-163

Mitigating System

Performance Index (MSPI)

Basis Document

71152A

Corrective

Action

Documents

Condition

Reports

108366, 145735, 10019562,

10029246, 10029822,

10030242, 10031127,

10031663, 10027491

71152A

Drawings

E-13KJ03A

Schematic Diagram Diesel

Gen KKJ01B Engine Control

(Start/Stop Circuit)

71152A

Drawings

E-13KJ03A

Schematic Diagram Diesel

Gen KKJ01A Engine Control

(Start/Stop Circuit)

71152A

Drawings

M-12KJ05

Piping and Instrumentation

Diagram Standby Diesel

Generator B Intake Exhaust,

F.O., and Start Air Sys.

71152A

Engineering

Changes

CP 20454

Kinectrics Relay/Contact Block

Replacement for EDG Room

Panels

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152A

Miscellaneous

M-018-00309

Instruction Manual for

Emergency Diesel Generator

System

W141

71152A

Procedures

CKL ZL-004

Turbine Building Reading

Sheet

2

71152A

Procedures

STS KJ-015B

Manual/Auto Fast Start, Sync

and Loading of EDG NE02

71152A

Procedures

SYS KJ-124

Post Maintenance Run of

Emergency Diesel Generator

B

71152A

Work Orders

WO 26620. 21-469171-006, 21-

469172-000, 56090,

21-469171-013

71152S

Corrective

Action

Documents

Condition

Reports

10027129, 10027148,

10031001, 10031493,

10032794, 10033122,

10033418, 10033639

71152S

Drawings

M-12GT01

Piping and Instrumentation

Diagram Containment Purge

Systems

71152S

Miscellaneous

M-018-00309

Instruction Manual for

Emergency Diesel Generator

System

W141

71152S

Procedures

AP 16E-002

Post Maintenance Testing

Development

21B

71152S

Procedures

AP 23AL-002

Heat Exchanger Program

71152S

Procedures

AP 23E-001

Emergency Diesel Generator

Reliability Program

71152S

Procedures

CKL ZL-005A

A EDG Operating Log

6A

71152S

Work Orders

WO

20-461655-004, 23-486310-

000, 23-486310-001,

23-486310-002

71153

Corrective

Action

Documents

Condition

Reports

10031603, 10031604

71153

Procedures

APF 06-002-

Emergency Action Levels

Technical Bases

43