IR 05000482/2021003

Integrated Inspection Report 05000482/2021003 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2021001, WC2021003 IR Ch

ML21302A194
Person / Time
Site:	Peach Bottom, Wolf Creek
Issue date:	11/05/2021
From:	Greg Werner NRC/RGN-IV/DRP
To:	Reasoner C Wolf Creek
References
IR 2021001
Download: ML21302A194 (25)

Text

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2021003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079/2021001

Dear Mr. Reasoner:

On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On October 7, 2021, the NRC inspectors discussed the results of this inspection with Mr. Jaime McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

NRC inspectors documented one finding of very low safety significance (Green) in the report that did not involve a violation of NRC requirements.

If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement 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 November 5, 2021 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 Reactor Projects Docket Nos. 05000482 and 07200079 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket Number: 05000482 and 07200079

License Number: NPF-42

Report Number: 05000482/2021003 and 07200079/2021001

Enterprise Identifier: I-2021-003-0031 and I-2021-001-0007

Licensee: Wolf Creek Nuclear Operating Corporation

Facility: Wolf Creek Generating Station and Independent Spent Fuel Storage Installation

Location: Burlington, KS

Inspection Dates: July 1, 2021 to September 30, 2021

Inspectors: L. Brookhart, Senior Spent Fuel Storage Inspector M. Davis, Trans And Storage Safety Inspector M. Doyle, Operations Engineer C. Henderson, Senior Resident Inspector J. Melfi, Project Engineer P. Patel, Structural Engineer G. Pick, Senior Reactor Inspector R. Rodriguez, Structural Engineer E. Simpson, Health Physicist C. Smith, Health Physicist J. Vera, Resident Inspector

Approved By: Gregory E. Werner, Chief Reactor Projects Branch B Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection and an independent spent fuel storage installation 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 Implement Critical Design Parameters for the Main Feedwater System During Digital Control System Modifications Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.12] - Avoid 71153 FIN 05000482/2021003-01 Complacency Open/Closed The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to ensure balance of plant control system vendor used critical design parameters for the nonsafety-related main feedwater system bypass regulating valves in accordance with Procedure AI 05-005, Modifications to Non-Controlled [structures, systems, and components], Revision 5. Procedure AI 05-005 implemented the licensee self--imposed standard to control the main feedwater system as controlled plant equipment which required configuration-control to conform with Title 10 Code of Federal Regulations Part 50,

Appendix B rules and regulations. As a result, operators observed oscillating and divergent water levels in all four steam generators that caused an automatic reactor trip.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000482/2021-003-00 Automatic Reactor Trip Due 71153 Closed to Low Steam Generator Level

PLANT STATUS

Wolf Creek Generating Station began the inspection period at full power. On August 18, 2021, an automatic reactor trip from 100 percent reactor occurred due to a loss of main feedwater flow to the B steam generator caused by a stem separation of the B main feedwater regulating valve.

The licensee commenced Forced Outage 25-02 to repair the B main feedwater regulating valve and performed extent of condition reviews of the remaining three main feedwater regulating valves. On August 21, 2021, the unit commenced reactor startup, and the reactor was made critical. The unit was returned to full power on August 22,

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time onsite as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities; and completed onsite portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and onsite. The inspections documented below met the objectives and requirements for completion of the IP.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Train B essential service water to emergency diesel generator jacket water and lube oil heat exchangers on July 9, 2021

(2) Train A electrical penetration cooling unit SGL15A on July 21, 2021

(3) Train A safety injection on September 23, 2021

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the component cooling water system on September 28, 2021.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) Electrical penetration room A, fire area A-18, on July 21, 2021

(2) Electrical penetration room B, fire area A-17, on July 21, 2021

(3) Essential service water pump house pump room B, fire area essential service water B, on August 4, 2021

(4) Safety injection pump room B, fire area A-4, on September 8, 2021

(5) Safety injection pump room A, fire Area A-2, on September 23, 2021

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on July 20, 2021.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Train B engineering safety feature 4160volt switchgear (NB02) room on August 5, 2021

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Train B essential service water electrical cable manhole MHE5B inspection on August 31, 2021

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (2 Samples)

The inspectors evaluated readiness and performance of:

(1) Train B emergency diesel generator jacket water heat exchanger on July 16, 2021

(2) Train A component cooling water heat exchanger on September 10, 2021

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on September 14, 2021.

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 control rod movement and parking on August 12, 2021.

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

(1) The inspectors observed and evaluated the annual licensed operator requalification exam on September 8, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

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

(1) Containment fan cooler supply breaker starter relay failures on August 5, 2021

(2) Adverse trend in valve program issues on September 7, 2021

(3) Safety injection system maintenance effectiveness review on September 23, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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) Train A essential service water manhole MHE3A and safety injection planned maintenance window on July 14, 2021

(2) Turbine driven auxiliary feedwater pump planned maintenance window on August 24, 2021

(3) Emergent work activities for a partial loss of power to train B balance of plant engineered safety feature actuation system cabinet SA036E during control room radiation monitor testing on September 3, 2021

(4) Emergency diesel generator A, 7-day planned maintenance window on September 14, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) Train B turbine drive auxiliary feedwater essential feedwater suction check valve operability determination on July 7, 2021

(2) Trains A and B containment coolers with support system inoperable during maintenance operability determination on August 4, 2021

(3) Train B battery charger momentary voltage drop when starting emergency diesel generator B supply fan operability determination on September 10, 2021

(4) Emergency exhaust system damper failure to reclutch following maintenance past operability determination on September 16, 2021

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) Ovation balance of plant digital control upgrade - main feedwater pump trip and turbine runback on September 10, 2021

(2) Manual operator actions with the emergency diesel generator paralleled with offsite power on September 16, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Train A safety injection pump and breaker maintenance post-maintenance testing on July 16, 2021

(2) Train A safety injection discharge header motor operated valve EMHV8812A post-maintenance testing on July 16, 2021

(3) Train B Emergency exhaust system non-radioactive tunnel supply downstream isolation damper, GLD0037, failure to reclutch following maintenance post-maintenance testing on July 23, 2021.

(4) Train A charging pump discharge header to boron injection tank isolation motor operated valve, EMHV8803A, packing adjustment post-maintenance testing on July 28, 2021.

(5) Main feedwater regulating valve B stem replacement post-maintenance testing on August 20, 2020

(6) Train A auxiliary feedwater pump and valve maintenance post-maintenance testing on September 22, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Train B component cooling water pumps B and D comprehensive inservice surveillance testing on July 8, 2021

(2) Trains A and B electrical penetration room cooler surveillance testing requirements on August 5, 2021

(3) Train A safety injection solid station protection system logic test on August 12, 2021

FLEX Testing (IP Section 03.02) (1 Sample)

(1) FLEX 500 kW diesel generator and reactor coolant system make up pump testing on September 7, 2021

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Emergency preparedness drill involving a complete loss of core exit thermocouple indication, loss of control room indications, and loss-of-coolant accident on August 18,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) July 1, 2020 through June 30, 2021

MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)

(1) July 1, 2020 through June 30, 2021

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) FLEX diesel generator testing operating experience on August 24, 2021

(2) Effectiveness of corrective actions related to the full implementation cyber security program inspection findings as described in NRC Cyber Security Inspection Report 05000482/2019410 (ML19268A037)

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

(1) The inspectors evaluated the reactor trip from 100 percent reactor power due to a loss of feedwater to steam generator B and licensees response on August 18, 2021.

Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000482/2021-003-00, "Automatic Reactor Trip Due to Low Steam Generator Level" (ADAMS Accession No. ML21193A078). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60856 - Review of 10 CFR 72.212(b) Evaluations

The inspection was conducted to determine if Wolf Creek Generating Station met the general license requirements of 10 CFR Part 72 before conducting operations to load their Independent Spent Fuel Storage Installation (ISFSI).

Review of 10 CFR 72.212(b) Evaluations===

(1) On August 16-19, 2021, the NRC conducted a team inspection of Wolf Creek Generating Station's 10 CFR Part 72 program implementation and 10 CFR 72.212 report prior to the licensee's first loading campaign, which is scheduled for the fall of 2021. Wolf Creek Generating Station has elected to become a 10 CFR Part 72 general licensee in accordance with 10 CFR 72.210. The licensee has selected the Transnuclear Americas LLC Nutech Horizontal Modular Storage Extended Optimized Storage (EOS) system. The licensee constructed the ISFSI storage pad in the spring of 2020 and built the EOS NUMHOMS in the fall of 2020, in accordance with the Transnuclear NUHOMS EOS Certificate of Compliance 72-1042, Amendment 1 and Final Safety Analysis Report, Revision 3.

The following programs, procedures, and calculations were inspected:

Site specific analysis that confirmed the licensee met the license conditions for flooding, lightning, blockage of inlet openings, off-normal temperature requirements, and snow and ice Evaluation to confirm annual dose equivalent would meet 10 CFR 72.104 and 72.106 requirements Evaluation under 10 CFR 50.59 of ISFSI's impact on the reactor facility and compliance to site's heavy load program Evaluation of the fuel building's crane to meet the criteria of NUREG 0554 Single-Failure-Proof Cranes for Nuclear Power Plants,"

Review of calculations for structural and seismic stability for the transfer cask on the fuel building crane and placement locations within the fuel building Work orders and procedures that the fuel building's crane meets ASME B30.2 for load testing and annual maintenance requirements Reviewed site's new Emergency Plan for inclusion of ISFSI specific emergencies Evaluation of ISFSI impact on the reactor Quality Assurance Plan Evaluation of the ISFSI's impact on the reactor facility's radiation protection plan Training program for qualification of Part 72 operations within the fuel building Training program and procedures for performing 10 CFR 72.48 evaluations Training program qualification for the updated Emergency Plan with ISFSI specific requirements Load testing and non-destructive testing records of special lifting devices used during loading operations Fuel selection procedures to ensure fuel contents meet license conditions Record retention program implementation for ISFSI records

Remaining items that have yet to be fully reviewed include:

Site specific analysis confirming license conditions for tornados, earthquake, fire and explosions, normal environmental temperatures, and soil liquefaction Matrix loading crane and roller trays structural and seismic analysis Training documentation for qualification of Part 72 operations outside at the ISFSI pad Review of site specific 10 CFR 72.48 changes, tests, and experiments Finalized 10 CFR 72.212 report

INSPECTION RESULTS

Failure to Implement Critical Design Parameters for the Main Feedwater System During Digital Control System Modifications Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.12] - Avoid 71153 FIN 05000482/2021003-01 Complacency Open/Closed The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to ensure balance of plant control system vendor used critical design parameters for the nonsafety-related main feedwater system bypass regulating valves in accordance with Procedure AI 05-005, Modifications to Non-Controlled SSCs, Revision 5.

Procedure AI 05-005 implemented the licensee self--imposed standard to control the main feedwater system as controlled plant equipment which required configuration-control toconform with Title 10 Code of Federal Regulations Part 50, Appendix B rules and regulations. As a result, operators observed oscillating and divergent water levels in all four steam generators that caused an automatic reactor trip.

Description:

During Refueling Outage (RF) 24, the licensee upgraded multiple nonsafety-related nuclear supply system control systems to the Ovation based distribution control system. These changes included new digital controls for the main feedwater system regulating valves and the associated bypass valves. The main feedwater system was a nonsafety-related SSC that was controlled in accordance with Procedure AI 05-005.

Procedure AI 05-005, Attachment A, classified the main feedwater system as controlled plant equipment. This designation implemented the self-imposed standard that configuration control for the main feedwater system conforms with 10 CFR Part 50, Appendix B rules and regulations. Therefore, the inspectors concluded the licensees self-imposed standard was to ensure modifications of the nonsafety-related main feedwater system to the Ovation based distribution control system was controlled in accordance with 10 CFR Part 50, Appendix B, Criterion III, which states, in part, that measures shall also be established for the selection and review suitability of application of material, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components.

On May 12, 2021, the licensee was performing a reactor startup following the completion of RF 24 when steam generator water levels began oscillating and diverging at approximately 8 percent reactor power while in automatic control. Operators took manual control of the main feedwater regulating bypass valves but were unable to restore levels prior to a steam generator low level automatic reactor trip. The cause of the automatic reactor trip was the low-power controller gains for the main feedwater bypass regulating valves were set too high. This led to a higher feedwater flow to the steam generators than needed for the feedwater system demand. This condition resulted in steam generator water level control instability causing oscillating and diverging water levels. The licensee entered this issue into their corrective action program as Condition Report 10005736, classified this a significant condition adverse to quality and performed a root cause evaluation. The root cause evaluation identified one root cause and one contributing cause associated with the automatic reactor trip that occurred on May 12, 2021. The root cause and contributing cause are as follows:

Root

Cause:

The licensees specific main feedwater bypass regulating valve characteristics and the impact of the feedwater control system designed were not fully recognized. This resulted in the incorrect control system tuning parameters and inadequate risk mitigation strategies for the initial power ascension following the implementation of the Ovation main feedwater digital control system. Specifically, the licensees vendor did not incorporate the stations main feedwater bypass regulating valve critical design parameters of a 4-inch bypass valve with a maximum flow coefficient of 150 for determining the initial tuning parameters for the valves during the Ovation upgrade. Instead, the vendor used a 6-inch bypass valve with a flow coefficient near double the value of the stations bypass valve flow coefficient. This resulted in the low-power controller gain values for the main feedwater bypass regulating valves being set too high. These parameters resulted in the steam generator water level control instability causing oscillating and diverging water levels, resulting in the May 12, 2021, automatic reactor trip.

Contributing cause: Throughout the Ovation modification design and implementation process, there was inadequate risk recognition and advocacy which resulted in missed opportunities for leaders to engage cross-functionally and make key decisions. For example, the licensees initial just-in-time training for the Ovation system modification was based on an analysis of training needs and focused on performing the reactor startup activities with the Ovation system. However, the licensee concluded the possible failures of all main feedwater bypass regulating valves, with oscillating and diverging steam generator water levels at low power, was not determined to be a likely failure even though it occurred on the plant training simulator. This similar event occurring on the plant training simulator provided the licensee with an opportunity to validate the vendor used the correct main feedwater system critical design parameters and their conclusion the plant training simulator was not comparable to the anticipated plant response when implementing the new main feedwater digital control system.

The inspectors reviewed the above information and concluded the licensee failed to implement the self-imposed standard to control the main feedwater system as a controlled plant equipment in accordance with Procedure AI 05-005. Specifically, the licensee failed to ensure the balance of plant control system vendor used critical design parameters for the main feedwater system bypass regulating valves.

Corrective Actions: The licensee implemented the following immediate corrective actions: 1. The initial controller gain values were updated for the main feedwater bypass regulating valves using the stations critical design parameters prior to commencing reactor startup on May 14, 2021; 2. The licensee performed additional just-in-time training to ensure licensed operators were familiar with manual digital control system for the main feedwater bypass regulating valves prior to the May 14, 2021 reactor startup. The corrective action to prevent recurrence was to update design drawings with a caution that a change to the valve critical design parameters could impact the Ovation feedwater control logic.

Corrective Action References: Condition Report 10005736

Performance Assessment:

Performance Deficiency: The licensees failure to ensure balance of plant control system vendor used critical design parameters for the main feedwater system bypass regulating valves was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the licensees failure to use the main feedwater system bypass regulation valve critical design parameters during balance of plant control system modification resulted in oscillating and divergent water levels in all four steam generators resulting in an automatic reactor trip.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 1, Section B.

The inspectors determined the finding was of very low safety significance (Green) because the finding did cause a reactor trip, but not the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition (e.g., loss of condenser, loss of feedwater).

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee failed to validate the vendor design control parameters for the main feedwater system bypass regulating valves and reevaluate the risk associated with oscillating and diverging water levels in all four steam generators, even when plant training simulator indicated the potential of this event to occur.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding.

EXIT MEETINGS AND DEBRIEFS

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

On July 28, 2021, the inspectors presented the cyber security problem identification and resolution inspection results to Mr. L. Lane, Director Strategic Engineering and other members of the licensee staff.

On September 14, 2021, the inspectors presented the Wolf Creek 2021 annual requalification inspection results to Mr. A. Servaes, Regulatory Exam Writer and other members of the licensee staff.

On October 7, 2021, the inspectors presented the integrated inspection results to Mr. J. McCoy, Site Vice President and other members of the licensee staff.

On October 7, 2021, the inspectors presented the Independent Spent Fuel Installation 72.212 Inspection results to Mr. C. Reasoner, Chief Executive Officer and Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60856 Engineering 50.59 Document Cask Handling Crane NUREG 0554/0612 Compliance 1

Evaluations Number 15044 Safety Analysis Report

60856 Engineering BED WO 21-Characterization of Fuel Assemblies and Control 07/27/2021

Evaluations 468230-001 Components Discharged through RF22

60856 Engineering Calc 30501-0506 NUHOMS HSM-MX Dose Rates and ISFSI Site Dose 0

Evaluations Analysis

60856 Engineering HG-C-003 Stability of Loaded Transfer Cask in all Planned 0

Evaluations Configurations in the Fuel Building

60856 Engineering HG-C-006 Heavy Loads Summary for Pool-to-Pad Operational 0

Evaluations Evolutions

60856 Engineering KE-C-019 Crane Structural Analysis and Trolley Evaluation 0

Evaluations

60856 Procedures AI 19C-001 Dry Cask Storage Loading Plan 0

60856 Procedures AP 06-002 Radiological Emergency Response Plan 23

60856 Procedures APF 06-002-02 Emergency Action Levels Technical Bases 1

71111.04 Calculations GL-M-002 Calculate Tube Plugging Allowance for Aerofin (Cu-Ni) Coils 0

for Electrical Penetration Room Coolers (SGL15A and

SGL15B)

71111.04 Calculations KJ-M-015 EKJ06A/B Thermal Performance Calculation 1

71111.04 Calculations KJ-M-017 Emergency Diesel Standby Generator (KKJ01 BB) Runtime 1

without ESW Flow

71111.04 Calculations XX-M-005 Evaluation of the UHS Maximum Temperature to Exceed 0

95F Design Basis Temperature Short Periods during the 30

Day Following a DBA

71111.04 Calculations XX-M-068 Tube Plugging Criteria for Safety-Related Room Cooler 2

(Aerofin AL6XN) Cooling Coils

71111.04 Corrective Action Condition Reports 10006569, 10007097, 10007129, 10007128

Documents

71111.04 Corrective Action Condition Report 10007353

Documents

Resulting from

Inspection

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings E-13KJ03B Schematic Diagram Diesel Generator KKJ01B Engine 6

Control (D/G Trips)

71111.04 Drawings M-12EF01 Piping Instrumentation Diagram Essential SVC Water 30

System

71111.04 Drawings M-12EF02 Piping and Instrumentation Essential SVC Water System 43

71111.04 Drawings M-12EG01 Piping & Instrumentation Diagram Component Cooling 26

Water System

71111.04 Drawings M-12EG02 Piping & Instrumentation Diagram Component Cooling 28

Water System

71111.04 Drawings M-12EG03 Piping & Instrumentation Diagram Component Cooling 19

Water System

71111.04 Drawings M-12GL01 Piping and Instrumentation Diagram Auxiliary Building HVAC13

71111.04 Drawings M-12KJ04 Piping and Instrumentation Diagram Standby Diesel 19

Generator B Cooling Water System

71111.04 Drawings M-12KJ06 Piping and Instrumentation Diagram Standby Diesel 22

Generator B Lube Oil System

71111.04 Engineering CCP 012774 EKJ06A/B Replacement Jacket Water Heat Exchangers 0

Changes

71111.04 Miscellaneous E-1F9915 Design Basis Document for OFN PR-017, Control Room 14

Evacuation

71111.04 Procedures AP 21G-001 Control of Locked Components Status 78A

71111.04 Procedures CKL EF-120 Essential Service Water Valve, Breaker and Switch Lineup56B

71111.04 Procedures CKL EG-120 Component Cooling Water System Valve Switch and 51

Breaker Lineup

71111.04 Procedures OFN RP-017 Control Room Evacuation 54

71111.04 Procedures STN EF-022B ESW Train B Post-LOCA Flow Balance 12A

71111.04 Procedures STN PE-037B ESW Train B Heat Exchanger Low and DP Trending 23

71111.04 Work Orders WO 17-432437-006

71111.05 Corrective Action Condition Report 10007600

Documents

71111.05 Corrective Action Condition Report 10009053

Documents

Resulting from

Inspection

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Drawings M-12LF02 Piping and Instrumentation Diagram Auxiliary Building Floor 03

and Equipment Drain System

71111.05 Drawings M-12LF04 Piping and Instrumentation Diagram Auxiliary Building Floor 01

and Equipment Drain System

71111.05 Miscellaneous E-1F9905 Fire Hazard Analysis 10

71111.05 Miscellaneous E-1F9910 Post Fire Safe Shutdown Area Analysis 13

71111.05 Procedures AP 10-106 Fire Preplans 21

71111.06 Calculations FL-08 Control Building Flooding 3

71111.06 Corrective Action Condition Reports 10004542, 10005554

Documents

71111.06 Corrective Action Condition Report 10008129

Documents

Resulting from

Inspection

71111.06 Drawings E-11NG20 MCC-NG02A 238

Sheet 11

71111.06 Drawings M-12EF01 Piping Instrumentation Diagram Essential SVC Water 30

System

71111.06 Drawings M-12KC02 Piping and Instrumentation Diagram Fire Protection System25

71111.06 Drawings M-12LE02 Piping and Instrumentation Diagram Control and Diesel Gen. 6

Bldg. Oily Waste System

71111.06 Drawings M-1G051 Equipment Locations Control and Diesel Gens BLDFS and 14

Comm. Corridor Plan EL. 2000-00 and EL. 2016-00

71111.06 Miscellaneous BAP-21-0353 Barrier Authorization Permit

71111.06 Miscellaneous WCRE-035 Boundary Matrix 8

71111.06 Procedures AI 21-016 Operator Time Critical Actions Validation 20

71111.06 Procedures ALR 00-008B Serv WTR Press HI LO 18

71111.06 Procedures ALR 00-049E CTRL BLD OW Sump Level Hi 8

71111.06 Procedures ALR 00-055A ESW PMP A Press LO 11A

71111.06 Procedures AP 21-004 Operator Response Time Program 4C

71111.06 Procedures OFN SG-003 Natural Events 37

71111.06 Work Orders WO 17-427039-000

71111.07A Calculations KJ-M-011 EKJ03A/B Thermal Performance Calculation 0

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.07A Calculations KJ-M-015 EKJ06A/B Thermal Performance Calculation 1

71111.07A Corrective Action Condition Reports 107702, 107706, 137997, 138950, 145929, 145940,

Documents 10002803, 10003532, 10003541, 10003543, 10003585,

10003642, 10003654, 10003697, 10003826, 10004111,

10004152, 10004284, 10004325, 10004276, 10004495

71111.07A Corrective Action Condition Report 10004457

Documents

Resulting from

Inspection

71111.07A Drawings M-1HX001 Heat Exchanger Tube Sheet Maps 85

71111.07A Miscellaneous M-018E Design Specification for Replacement Jacket Water Heat 2

Exchangers ASME Code Section III Class 3

71111.07A Procedures AP 23L-002 Heat Exchanger Program 5

71111.07A Procedures STN PE-037B ESW Train B Heat Exchanger Flow and DP Trending 23

71111.07A Work Orders WO 16-418115-000, 17-433842-000, 18-447320-000,

19-440206-000, 19-451425-000, 19-456598-000,

20-457635-000, 20-458813-000, 20-458813-002,

20-461902-000, 20-464226-000

71111.11A Miscellaneous Wolf Creek ARQ Wolf Creek ARQ exam results 09/14/2021

exam results

71111.11Q Procedures STN SF-001 Control Rod Parking 21A

71111.11Q Work Orders WO 21-468846-000

71111.12 Calculations SA-88-015 Determination of the SI Flowrate under HL Injection Mode 0

71111.12 Corrective Action Condition Reports 109647, 110725, 123103, 125945, 127042, 134338, 134339,

Documents 141615, 10001654, 10005727, 10006141, 10006569,

10007097, 10007128, 10007387, 10007433, 10007439,

10008024, 10008863

71111.12 Corrective Action Condition Reports 10007665, 10008147, 10009043

Documents

Resulting from

Inspection

71111.12 Drawings M-12BB01 Piping and Instrumentation Diagram Reactor Coolant 43

System

71111.12 Drawings M-12EM01 Piping and Instrumentation Diagram High Pressure Coolant 46

Inspection Type Designation Description or Title Revision or

Procedure Date

Injection System

71111.12 Drawings M-12EP01 Piping and Instrumentation Diagram Accumulator Safety 17

Injection

71111.12 Engineering DCP 020393 EDG Supply Fan Motor Starters Replacement 0

Changes

71111.12 Miscellaneous E-018-00189 Qualification and Test Summary Report 11W

71111.12 Miscellaneous EDSD-I Equipment Qualification Design Basis Document 16

71111.12 Miscellaneous M-000 Mechanical/Nuclear Design Criteria for Wolf Creek 20

Generating Station

71111.12 Miscellaneous WCOP-02 Inservice Testing Program for Pumps, Valves, and Snubbers16

71111.12 Procedures AI 29B-002 Check Valve Condition Monitoring Program 8A

71111.12 Procedures ELE-007 NG001T - NG004T Motor Control Center Inspection, 1

Cleaning and Testing

71111.12 Procedures EM-M-036 Establishment of the Safety Injection Pump Comprehensive 0

Test Error Allowance and Minimum Operability Limit Curve

71111.12 Procedures STS CV-103 Inservice Testing Check Valve Condition Monitoring for 6

BB8949A/B/C/D

71111.12 Procedures STS CV-210A ECCS SI Comprehensive Pump and Inservice Check Valve 28

Test

71111.12 Procedures STS EJ-209A Train A RHR System Inservice Valve Test 5

71111.12 Procedures STS EJ-209B Train B RHR System Inservice Valve Test 5

71111.12 Procedures STS PE-019E RCS Isolation Check Valve Leak Test 34

71111.12 Procedures SYS GN-120 Containment Cooling System Operation 5

71111.12 Work Orders WO 13-374331-000, 18-440567-009, 20-462172-000

71111.13 Calculations NAI-1878-001 Wolf Creek HELB Analysis 0

71111.13 Corrective Action Condition Reports 84848, 10008360, 10008523, 10008827, 10008829,

Documents 10009004, 10009065, 10009124

71111.13 Corrective Action Condition Report 10008652

Documents

Resulting from

Inspection

71111.13 Drawings J-104-00390 Logic Block Diagram ESFAS W08

71111.13 Drawings KD-7496 Sheet 1 One Line Diagram 73

71111.13 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 32

Inspection Type Designation Description or Title Revision or

Procedure Date

System

71111.13 Miscellaneous BAP-21-0349 Breach Authorization Permit TDAFW TESO Work 0

71111.13 Miscellaneous EQSD-I Equipment Qualification Design Basis Document 14

71111.13 Miscellaneous WCRE-35 Boundary Matrix 8

71111.13 Procedures AI 22C-013 Protected Equipment Program 23A

71111.13 Procedures AP 10-104 Breach Authorization 39

71111.13 Procedures AP 22C-003 On-Line Nuclear Safety and Generation Risk Assessment 24

71111.13 Procedures AP 22C-007 Risk Management and Contingency Planning 11

71111.13 Procedures AP 22C-008 Qualitative Risk Management 5

71111.13 Procedures EMG C-0 Loss of All AC Power 45

71111.13 Procedures EMG E-0 Reactor Trip or Safety Injection 44

71111.13 Procedures EMG ES-02 Reactor Trip Response 41

71111.13 Procedures EMG FR-H1 Response to Loss of Secondary Heat Sink 37

71111.13 Procedures OFN NB-030 Loss of AC Emergency Bus NB01 (NB02) 39A

71111.13 Procedures STS IC-455B Channel Calibration Control Room Air Intake Radiation 18A

Monitor GK RE-0004

71111.13 Procedures SYS AP-122 Non-Safety Aux Feed Pump Operation 13

71111.13 Procedures SYS SY-120 Sharpe Diesel Operation and Alignment to Site 14A

71111.13 Work Orders WO 20-466623-001, 20-458883-018, 21-474284-000

71111.15 Calculations EF-M-80 UHS Inventory Losses form ESW through the AFW System 0

71111.15 Calculations GL-M-005 Electrical Penetration Room Temperature with Inoperable 0

Room Cooler

71111.15 Calculations HV-288 Loss of Ventilation 0

71111.15 Corrective Action Condition Reports 10007131, 10007263, 10007622

Documents

71111.15 Corrective Action Condition Report 10009180

Documents

Resulting from

Inspection

71111.15 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 32

System

71111.15 Engineering CCP 09816 Inoperable Electrical Penetration Room Cooler (SGL15A/B)0

Changes

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Miscellaneous E-018-00189 Qualification and Test Summary Report 11W

71111.15 Miscellaneous EQSD-I Equipment Qualification Design Basis Document 14

71111.15 Miscellaneous EQSD-II Equipment Qualification Design Basis Document 23

71111.15 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 12

71111.15 Procedures AP 26C-004 Operability Determination and Functionality Assessment 44

71111.15 Procedures MPE RC-001 Room Cooler Maintenance 11

71111.15 Procedures MPE VD-001 627A Ventilation Damper Maintenance 17

71111.15 Procedures SYS GL-200 Inoperable Penetration Room Cooler 13A

71111.15 Procedures SYS OQT-001B Operations B Train Quarterly Tasks 26

71111.15 Work Orders WO 20-466019-000, 20-466019-001

71111.18 Calculations GM-M-002 Diesel Generator Building Minimum Room Temperature 1

71111.18 Calculations KJ-M-017 Emergency Diesel Standby Generator (KKJ01 BB) Runtime 1

without ESW Flow

71111.18 Corrective Action Condition Reports 10003002, 10003106, 10003334, 10003523, 10003525,

Documents 10003731, 10004244, 10004269, 10007567

71111.18 Corrective Action Condition Reports 10007846, 10008687

Documents

Resulting from

Inspection

71111.18 Miscellaneous M-018-00155 Operation of Engine without Cooling Water 2

71111.18 Procedures ALR 00-120A MFP A Trip 13

71111.18 Procedures ALR 00-123A MFP B Trip 14

71111.18 Procedures ALR 00-123A MFP B Trip 15

71111.18 Procedures BD-EMG E-0 Reactor Trip or Safety Injection 29A

71111.18 Procedures EMG E-0 Reactor Trip or Safety Injection 44

71111.18 Procedures MFP A Trip MFP A Trip 14

71111.18 Procedures OFN EF-033 Loss of Essential Service Water 23

71111.18 Procedures OFN NB-042 Loss of Offsite Power to NB01 (NB02) with EDG Paralleled 15

71111.19 Corrective Action Condition Reports 10005026, 10007439, 10008456, 10008543

Documents

71111.19 Miscellaneous WCOP-02 Inservice Testing Program for Pumps, Valves, and Snubbers16

71111.19 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Program 12

71111.19 Procedures AI 23D-002 Motor Operated Valve Calculation Program 3

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Procedures AP 16E-002 Post Maintenance Testing Development 20A

71111.19 Procedures AP 23D-001 Motor Operated Valve Program 4

71111.19 Procedures MPM LT-001 Limitorque Operator Minor Maintenance, Lubrication, and 15

Inspection

71111.19 Procedures STN EM-201 Safety Injection Valve Test 14

71111.19 Procedures STS AE-211 Main Feed Reg Valve Inservice Test 5

71111.19 Procedures STS AL-101 MDAFW Pump A Inservice Pump Test 46

71111.19 Procedures STS EM-100A Safety Injection Pump A Inservice Pump Test 43

71111.19 Procedures STS VT-001 Verification of OMN-1, MOV Exercise Requirements 6

71111.19 Work Orders WO 15-399593-001, 15-399593-018, 15-399593-021,

20-466803-000, 20-467625-000, 20-467625-001,

21-470469-000, 21-470469-001, 21-473455-007,

21-473455-008, 21-473455-013

71111.22 Calculations FD-13-008 RCS FLEX Hydraulic Evaluation 0

71111.22 Corrective Action Condition Reports 139748, 142288, 142515, 145234, 10000718, 10006728

Documents

71111.22 Corrective Action Condition Report 10007983

Documents

Resulting from

Inspection

71111.22 Miscellaneous WCNOC-183 Operations and Maintenance Manual RCS Pump Cat Triplex W01

353 HS.AIP Plunger Pump rated 20 GPM @ 1650 psig

71111.22 Procedures AP 16E-002 Post Maintenance Testing Equipment 20A

71111.22 Procedures AP 21A-002 Diverse and Flexible Coping Mitigating Strategies (FLEX) 3

Program

71111.22 Procedures AP 23L-002 Heat Exchanger Program 5

71111.22 Procedures STN PE-036 Safety Related Room Cooler Heat Transfer Verification and 17

Performance Trending

71111.22 Procedures STN PE-037A ESW Train A Heat Exchanger Flow and DP Trending 21

71111.22 Procedures STN PE-037B ESW Train A Heat Exchanger Flow and DP Trending 23

71111.22 Procedures STS EG-101B Component Cooling Water Pumps B/D Comprehensive 7B

Pump Test

71111.22 Procedures STS IC-211 Actuation Logic Test Train A Solid State Protection System37A

71111.22 Procedures SYS FD-001 Operations Monthly FLEX Tasks 7

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Procedures SYS FD-002 Operations Annual FLEX Tasks 3

71111.22 Work Orders WO 10-323422-000, 11-338649-000, 12-357297-000,

18-446961-000, 18-446961-001, 19-457078-005,

19-457425-000, 20-457635-000, 20-463186-002,

20-463186-010, 20-464266-000, 20-465658-000,

20-465658-002, 20-467211-000, 20-467211-001,

20-467213-000, 20-467458-000, 21-468259-000,

21-472930-000

71114.06 Corrective Action Condition Reports 10008457, 10008465, 10008468

Documents

71114.06 Corrective Action Condition Report 10008633

Documents

Resulting from

Inspection

71114.06 Procedures ALR 00-130C ESF N2 ACC Press LoLo 8

71114.06 Procedures ALR 00-130D ESF N2 ACC Press Lo 11

71151 Corrective Action Condition Report 10001662

Documents

71151 Miscellaneous WCNOC-163 Mitigating System Performance Index Basis Document 13

71151 Procedures FSG-05 Initial Assessment and FLEX Equipment Staging 3

71152 Calculations DAR-PEUS-12-6 FLEX Electrical Conceptual Design for the Wolf Creek 1

Nuclear Operating Corporation

71152 Calculations FD-E-001 FD System Electrical Calculations 2

71152 Corrective Action Condition Reports 139748, 142288, 142515, 145234, 128958, 133406, 133814,

Documents 134405, 134406, 134409, 141390, 10003270, 10004822,

10000718

71152 Corrective Action Condition Report 10007628

Documents

Resulting from

Inspection

71152 Drawings CYBER-C-0001 Cyber Security Network Block Diagram E

71152 Miscellaneous AC-VULN-Windows Server 2003 and Windows XP Vulnerabilities 05/26/2021

10003270 identified through CVEs

71152 Miscellaneous AIF 15D-028-08 Critical System Administrative Guide 2

Inspection Type Designation Description or Title Revision or

Procedure Date

71152 Miscellaneous LCM-20210405 SCS-LCM-202993.00, Security Computer System 0

71152 Miscellaneous RC-VULN-Windows Server 2003 and Windows XP Vulnerabilities 05/26/2021

10003270 identified through CVEs

71152 Miscellaneous WCNOC-185 Beyond Design Basis Flex Equipment Operations and W02

Maintenance Manual 500 kW Generator C15 Model

71152 Miscellaneous WO 11-0019 Cyber Security Plan 1

71152 Procedures AI 15D-020 Defense-in-Depth Cyber Security Protective Strategy 7

71152 Procedures AI 15D-027 Ongoing Monitoring & Vulnerability Analysis (OM&VA) 3

71152 Procedures AP 15D-008 Wolf Creek Cyber Security Program 7

71152 Procedures FSG-08 Alternate RCS Boration 2

71152 Work Orders WO 18-443033-001, 20-457258-000, 20-458235-000,

20-460439-000, 20-461349-000, 20-463623-000,

20-464828-000, 20-464837-000, 20-464838-000,

20-464839-000, 20-464840-000, 20-464840-000,

20-464842-000, 20-464843-000, 20-464844-000,

20-469726-000

71153 Corrective Action Condition Report 10008456

Documents

71153 Procedures EMG E-0 Reactor Trip or Safety Injection 44

71153 Procedures EMG ES-02 Reactor Trip Response 41

71153 Work Orders WO 21-473455-015, 21-473455-016, 21-473455-017,

21-473455-018

2