IR 05000482/2021004

Integrated Inspection Report 05000482/2021004 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2021002

ML22012A444
Person / Time
Site:	Peach Bottom, Wolf Creek
Issue date:	01/19/2022
From:	Greg Werner NRC/RGN-IV/DRP/RPB-B
To:	Reasoner C Wolf Creek
References
IR /2021002, IR 2021004
Download: ML22012A444 (28)

Text

January 19, 2022

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2021004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079/2021002

Dear Mr. Reasoner:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On January 13, 2022, the NRC inspectors discussed the results of this inspection with Mr. B. Bayer, General Manager, Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

Two findings of very low safety significance (Green) are documented in this report. One of these findings involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Wolf Creek Generating Station.

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 Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Signed by Werner, Gregory on 01/19/22 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: 05000482/2021004 and 07200079/2021002 Enterprise Identifier: I-2021-004-0119 and I-2021-002-0000 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station and Independent Spent Fuel Storage Installation Location: Burlington, KS Inspection Dates: October 1, 2021 to December 31, 2021 Inspectors: R. Alexander, Senior Emergency Preparedness Inspector D. Antonangeli, Health Physicist L. Brookhart, Senior Spent Fuel Storage Inspector M. Davis, Transportation and Storage Safety Inspector N. Greene, Senior Health Physicist C. Henderson, Senior Resident Inspector C. Smith, Health Physicist H. Strittmatter, Project Engineer 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 Reestablish Station Blackout Diesel Generator Preventive Maintenance Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.13] - 71111.12 Systems FIN 05000482/2021004-01 Consistent Open/Closed Process The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to reestablish annual vendor recommended preventive maintenance for the station blackout diesel generators starting battery banks in accordance with Procedure AP 16B-003, Planning and Scheduling Preventive Maintenance, Revision 8A. This condition resulted in the undetected degradation of the starting battery bank which resulted in the station blackout diesel generator C failure to start on November 1, 2021.

Failure to Correct a Condition Adverse to Quality Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.2] - 71152 Systems NCV 05000482/2021004-02 Evaluation Open/Closed The inspectors reviewed a self-revealed, Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion XVI, Corrective Action, for the licensees failure to correct a condition adverse to quality. Specifically, the licensee failed to correct potential short circuits incandescent lightbulbs and their associated sockets that result in inoperability of safety-related equipment. This condition resulted in the emergency diesel generator B lockout relay actuating and preventing its associated output breaker from closing, resulting in emergency diesel generator B being declared inoperable.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000482/2021004-00 Low Steam Generator Level 71153 Closed due to Main Feedwater Valve Failure Caused Automatic Reactor Trip

PLANT STATUS

Wolf Creek Generating Station began the inspection period at full power, except for seven occasions during the quarter when the licensee reduced power to 70 percent for flexible power operations (based on daily market demand) and returned to full power after each occasion.

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, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

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

(1) Train B Class 1E electrical equipment air conditioning unit in recirculation mode on November 1, 2021

(2) Safety injection accumulator A, B, C, and D aligned to vent to containment to lower accumulator pressure on November 17, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Essential service water vertical loop chase, fire area ESWC, on October 8, 2021

(2) Fire impairments during train B Class 1E electrical equipment air conditioning system maintenance, fire areas C-9, C-10, C-15, and C-16, on October 26, 2021

(3) Upper cable spreading room, fire area C-22, on November 15, 2021

(4) Breach authorizations during loss of central chilled water system, fire areas A-16 and A-21, on November 17, 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 operator performance during power changes as part of flexible power operations on October 20, 2021.

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

(1) The inspectors observed and evaluated simulator training activities on November 15, 2021.

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) Main feedwater system regulating valve failures on November 15, 2021

(2) Station blackout diesel generator C maintenance effectiveness on December 6, 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) Emergency diesel generator B emergent troubleshooting and corrective maintenance due to output breaker lockout on October 7, 2021

(2) Train A Class 1E electrical equipment air conditioning unit maintenance window extended due to compressor failure on October 26, 2021

(3) Station blackout diesel generator C failure to start emergent troubleshooting and corrective maintenance due to a failed battery on November 3, 2021

(4) Nonsafety-related chill water pump failure emergent work, auxiliary building envelope verification due to breach permits on November 17, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

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

(1) Train B component cooling water system with component cooling water pump B inoperable due to an oil leak operability determination on November 15, 2021

(2) Loop 1 overtemperature delta-T setpoint spikes operability determination on November 17, 2021

(3) Emergency diesel generator B 186-2 lockout relay light bulb failure causing inoperability common cause on December 3, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

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

(1) Train A Class 1E electrical equipment air conditioning compressor replacement post-maintenance testing on November 4, 2021

(2) Station blackout diesel generator C battery replacement post-maintenance testing on November 10, 2021

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated the following recently submitted emergency action level and emergency plan changes, and the associated change process evaluations per 10 CFR 50.54(q):

AP 06-002, Radiological Emergency Response Plan, Revision 22; effective 10/7/2021 APF 06-002-02, Emergency Action Levels Technical Bases, Revision 1; effective 10/7/2021 APF 06-002-03, EAL Classification Matrix, Revision 1; effective 10/7/2021 EPP 06-007, Emergency Notifications, Revision 27; effective 8/2/2021 EPP 06-006, Protective Action Recommendations, Revision 10A; effective 7/1/2021 EPP 06-012, Dose Assessment, Revision 17B; effective 6/8/2021 Elimination of EPP 06-019, Alert and Notification System Sirens, Revision 10; effective 6/8/2021 This evaluation does not constitute NRC approval.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensees radiological work planning. The inspectors reviewed the following radiation work permits (RWP):

(1) RWP 191000, "Radiation Protection Rover Coverage," Revision 0

(2) RWP 194207, "Reactor Coolant Pump Team & Preventative Maintenance,"

Revision 0

(3) RWP 213220, "Primary Side Steam Generator Eddy Current Testing and Zero Entry Nozzle Dam," Revision 1

(4) RWP 214199, "Secondary Side Steam Generator Foreign Object Search/Retrieval and Visual Inspections," Revision 0

(5) RWP 214200, "Secondary Side Steam Generator Sludge Lance," Revision 0 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)

The inspectors evaluated dose estimates and exposure tracking. The inspectors reviewed the following activities:

(1) RWP 194482, "Remove/Install Canopy Seal Weld Clamps," Revision 1

(2) RWP 194483, "Reactor Vessel Head Reassembly to Include Canopy Seal Clamp,"

Revision 0

(3) RWP 213057, "Under Reactor Head Entries for Electric Discharge Machining,"

Revision 4

(4) RWP 216020, "Reactor Vessel Head Lift Preparation and Post Head Set Work Activities," Revision 0

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the internal dosimetry program implementation. The inspectors reviewed the following:

(1) Whole Body Counts Internal dose calculation for personnel contamination Event 7803, dated October 27, 2019 Internal dose calculation for personnel contamination Event 7459, dated April 21, 2021 Internal dose calculation for personnel contamination Event 7865, dated May 01, 2021

(2) Dose Assessments Performed Using Air Sampling and Derived Air Concentration-Hour (DAC) Monitoring Air Sample 19-0483 with DAC Hours Assigned, dated October 19, 2019 Air Sample 20-0102 with DAC Hours Assigned, dated September 16, 2020 Air Sample 21-0607 with DAC hours assigned, dated April 17, 2021

Special Dosimetric Situations (IP Section 03.04) (3 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Implementation of requirements to manage radiation protection of declared pregnant workers for three of their workers

(2) Application of NRC-approved external dosimetry methods (i.e. EDEX) for five of their workers

(3) Neutron dosimetry evaluation, dated April 30,

OTHER ACTIVITIES - BASELINE

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

MS08: Heat Removal Systems (IP Section 02.07) ===

(1) October 1, 2020, through September 30, 2021

MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)

(1) October 1, 2020, through September 30, 2021

EP01: Drill/Exercise Performance Sample (IP Section 02.12) (1 Sample)

(1) July 1, 2020 through September 30, 2021 EP02: Emergency Response Organization Drill Participation (IP Section 02.13) (1 Sample)

(1) July 1, 2020 through September 30, 2021 EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14)

In that the licensee transitioned its alert and notification system to a purely nonsiren-based system in April 2020, the ANS performance indicator and associated data is no longer required to be reported by Wolf Creek, and thus is not subject to further inspection/verification per IP 71151. Evaluation of the licensee's nonsiren-based ANS is completed separately per IP 71114.02.

71152 - Problem Identification and Resolution (PI&R)

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees system and program health reports for engineering for potential adverse trends that might be indicative of a more significant safety issue. Specifically, the inspectors reviewed actions to address identified adverse trends that might indicate the existence of a more significant safety issue and noted a negative trend in corrective actions effectiveness followup failures.

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

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

(1) Emergency diesel generator B unplanned inoperability due to 186-2 lockout relay circuit light bulb failure on November 3, 2021

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

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

(1) LER 05000482/2021-004-00, Low Steam Generator Level due to Main Feedwater Valve Failure Caused Automatic Reactor Trip (ADAMS Accession No. ML21291A262). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60854 - Preoperational Testing of an Independent Spent Fuel Storage Installation (ISFSI) Determine by direct observation and independent evaluation whether the licensee had developed, implemented, and evaluated preoperational testing activities to safely load spent fuel from site's spent fuel pool to the ISFSI and safely retrieve spent fuel from the ISFSI and transfer it back to the licensee's spent fuel pool.

Preoperational Testing of an ISFSI ===

(1) 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 (TN) Nutech Horizontal Modular Storage (NUHOMS)

Extended Optimized Storage (EOS) system. The licensee constructed the ISFSI storage pad in the Spring of 2020 and built the EOS Matrix Horizontal Storage Modules (HSMs) in the Fall of 2020, in accordance with the TN NUHOMS EOS Certificate of Compliance 72-1042, Amendment 1 and Final Safety Analysis Report, Revision 3. On November 1-4, 2021, inspectors performed an onsite inspection to observe and evaluate Wolf Creek Generating Station's preoperational testing and training exercises. These operations are required to be performed by a general licensee prior to the use of the system to store spent fuel assemblies. During the inspection period, inspectors specifically observed the following demonstrations that were successfully completed by the licensee:

(1) Fuel loading with a dummy fuel assembly (Condition 9.a.)

(2) Transfer cask down-ending and transfer to the ISFSI using a weighted canister (Condition 9.c.)

(3) Dry shielded canister (DSC) transfer to the HSM using a weighted canister (Condition 9.d)

(4) DSC retrieval from the HSM using a weighted canister (Condition 9.e.)

Additionally, the licensee closed open items from the previous preoperational dry runs performed in June of 2020 (CR 143652), which closed and completed Condition 9.g.

(flooding of the DSC). The licensee has successfully completed all preoperational dry run activities required by the Certificate of Compliance 72-1042.

===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 ISFSI.

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

(1) During the inspection period (October 1-December 31, 2021), the inspectors continued the inspection of Wolf Creek's programs, procedures, and calculations performed by the licensee to meet the requirements of 10 CFR Part 72. Specifically, the inspectors completed the review of:

Site specific analysis confirming license conditions for tornados, earthquakes, fire and explosions, normal environmental temperatures, soil liquefaction, and structural evaluations of dry cask systems and components Training documentation for qualification of Part 72 operations outside at the ISFSI pad Review of site specific 10 CFR 72.48 and 10 CFR 50.59 changes, tests, and experiments associated with implementation of the EOS system at Wolf Creek.

The only remaining item that has yet to be fully reviewed included the site's finalized 10 CFR 72.212 report.

INSPECTION RESULTS

Failure to Reestablish Station Blackout Diesel Generator Preventive Maintenance Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.13] - 71111.12 Systems FIN 05000482/2021004-01 Consistent Open/Closed Process The inspectors reviewed a self-revealed, Green finding associated with the licensees failure to reestablish annual vendor recommended preventive maintenance for the station blackout diesel generators starting battery banks in accordance with Procedure AP 16B-003, Planning and Scheduling Preventive Maintenance, Revision 8A. This condition resulted in the undetected degradation of the starting battery bank which resulted in the station blackout diesel generator C failure to start on November 1, 2021.

Description:

On November 1, 2021, the licensee performed Procedure STN KU-010, Station Blackout Diesel and Non-Safety Auxiliary Feedwater Water Pump Test, Revision 13, for station blackout (SBO) diesel generator's (DG) B and C when SBO DG C failed to start. The licensee commenced troubleshooting, with vendor support, and identified two of the four starting batteries were faulted. This condition resulted in insufficient starting current to start SBO DG C. In response, the licensee replaced the two faulted batteries for SBO DG C and it was successfully started and ran on November 3, 2021. Additionally, the licensee performed Procedure STN KU-010 for SBO DG A and B successfully demonstrating they could be started with their starting batteries. The licensee entered this issue into their corrective action program as Condition Report (CR) 10010238 and performed an equipment performance evaluation. The equipment performance evaluation identified that the annual electrical preventive maintenance (PM) tasks were deleted when implementing the PM change under Work Order 19-452257-000 in accordance with Procedure AI 16B-002, Preventive Maintenance Change Process, Revision 15A, and entered this condition into their corrective action program as CR 10010613.

The inspectors reviewed equipment performance evaluation documented in CR 10010283, CR 10010613, and Procedures AP 16B-003, Planning and Scheduling Preventive Maintenance, Revision 8A, and AI 16B-002, Preventive Maintenance Change Process, Revision 15A, and identified the following:

Procedure AP 16B-003, step 6.2 required, in part, that when developing PM activities, the licensee consider vendor recommendations. The licensee initially established the vendor recommended PM activities of replacing the starting batteries for SBO DGs A, B, and C on a frequency of 3 to 5 years with annual electrical checks to ensure the starting batteries where capable of performing their design function of starting SBO DGs.

Procedure AI 16B-002 step 6.1.3 stated, in part, that it is the responsibility of the maintenance department to determine the best, safest and most efficient way to conduct PM tasks, that thorough notation of the changes must be documented in a preventative maintenance change (PMC), and that the documentation shall clearly state what was changed, deleted, or combined.

In December 2019, the licensee implemented a PMC package to streamline and reorganize the maintenance regimen for the SBO DGs in accordance with Procedure AI 16B-002. The PMC deleted all the existing PM tasks and had a task to reestablish the relevant PM activities for each individual SBO DGs. However, the licensee failed to reestablish the vendor recommended annual electrical tasks associated with the 3 to 5-year battery replacement and had no justification for not including the PM activity. This resulted in the licensees failure to detect the two out of four faulted starting batteries for SBO DG C prior to November 1, 2021.

The inspectors concluded that the licensee failed to implement the self-imposed standard in accordance with Procedure AP 16B-003, step 6.2, to consider vendor recommendations when reestablishing the SBO DG starting battery vendor recommended 3-to-5-year replacement frequency with annual electrical checks. This resulted in failure to reestablish annual battery PM and meet the self-imposed standard in accordance with Procedure AP 16B-003.

Corrective Actions: Reestablish the annual electrical PM tasks for the SBO DGs and the battery start cart.

Corrective Action References: CRs 10010238 and 10010613

Performance Assessment:

Performance Deficiency: The licensees failure to reestablish the vendor recommended SBO DG starting battery PM in accordance with Procedure AP 16B-003 was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to maintain vendor recommended maintenance procedures for the SBO DGs inserted a latent vulnerability in all three of the SBO DGs, in that the starting batteries on all the SBO DGs could be degraded and resulted in the failure of SBO DG C to start on November 1, 2021.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, the finding was determined to be very low safety significance (Green) because it:

(1) was not a design deficiency,

(2) did not represent a loss of system and/or function,

(3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,

(4) did not represent a loss of the probabilistic assessment (PRA) function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

(5) did not represent a loss of a PRA system and/or function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

(6) did not result in the loss of a high safety-significant, nontechnical specification train.

Cross-Cutting Aspect: H.13 - Consistent Process: Individuals use a consistent, systematic approach to make decisions. Risk insights are incorporated as appropriate. Specifically, the licensee failed to demonstrate an understanding of the PMC process in accordance with Procedure AI 16B-002 and use it consistently when reestablishing the PM for each of the SBO DGs. This resulted in failure to reestablish annual battery PM.

Enforcement:

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

Failure to Correct a Condition Adverse to Quality Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.2] - 71152 Systems NCV 05000482/2021004-02 Evaluation Open/Closed The inspectors reviewed a self-revealed, Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations, Part 50 (10 CFR Part 50), Appendix B, Criterion XVI, Corrective Action, for the licensees failure to correct a condition adverse to quality. Specifically, the licensee failed to correct potential short circuits incandescent lightbulbs and their associated sockets that result in inoperability of safety-related equipment.

This condition resulted in the emergency diesel generator B lockout relay actuating and preventing its associated output breaker from closing, resulting in emergency diesel generator B being declared inoperable.

Description:

On October 1, 2021, the licensee received emergency diesel generator (EDG) B trouble alarm due to 186-2/DG lockout relay inadvertently actuating due to a fault within the indicating light circuit bulb F series socket when the 120PSB incandescent light bulb burned out. This caused a short within the bulb socket bypassing the internal resistor causing the 186-2/DG lockout relay actuation preventing closure of EDG B output breaker. This condition would have prevented EDG B from energizing the train B safety-related 4160 V bus during a loss of offsite power, therefore the licensee declared EDG B inoperable until the light bulb was removed, and the 186-2/DG lockout relay was reset. The licensee entered this issue into their corrective action program as CR 10009585 and 10009587. Additionally, the licensee performed an equipment performance evaluation and a common cause evaluation.

The inspectors reviewed the equipment performance evaluation documented in CR 10009585, two common causes documented in CRs 10009587 and 140866, previous operating experience, and noted the following:

CR 2004-1024: Documented operating experience from another plant with a similar EDG design for a failed light bulb for the 186-2/DG lockout relay circuit on the EDG B output breaker. The bulb was replaced, and the lockout condition was reset. The bulb apparently failed such that it shorted and energized the 186-2/DG lockout relay.

The bulb which failed was a slide-in, friction-fit type bulb which had visual damage at the base of the bulb. No corrective actions were taken by the licensee based on the external operating experience documented in CR 2004-1024. However this operating experience was part of the common cause evaluation documented in CR 140866.

CR 140271: On February 3, 2020, the licensee received a status panel alarm for EDG B, and it was discovered the OFF light (120PSB incandescent bulb) for the EDG B fuel oil transfer pump had broken off while in the F series socket when the operator was changing the light bulb. The breaker for the EDG B fuel oil transfer pump remained closed, but the 1-amp fuses were found blown due a short to ground within the socket. This condition prevented the pump from running due to a loss of control power. The fuses and light bulb were replaced to correct the issue.

CR 141515: On March 24, 2020, the licensee observed the safety-related swing battery charger, NK25, was reading 94 Vdc, instead of the required 133 Vdc. The licensee investigation identified a blown 120PSB incandescent bulb and control power fuses. The licensee replaced the light bulb and control power fuses.

CR 141532: On March 25, 2020, NK25 voltage was 105 Vdc, instead of the required 133 Vdc, and the AC power light also appeared to be burned out. This was due to the loose bulb socket that was missed during the initial investigation conducted under CR 141515. The bulb socket was loosened by improper bulb replacement. The 120PSB bulbs are blade type and slide in and out. They are not designed to be twisted. The twisting motion can loosen the socket from the panel or crush and break the bulb causing a short to ground.

CR 140866: This CR evaluated the 2020 trend of loss of control power issues that had caused inoperability of safety-related equipment, which also included an external operating experience review of CR 2004-1024. The licensee concluded there was a vulnerability with proper replacement of the 120PSB incandescent bulbs. The corrective action was to replace the 120PSB bulbs with light-emitting diode (LED)equivalents. The LED 120PSB bulbs were direct replacement for T2 slide based miniature incandescent lamps. Change Package 20403 was approved in May 2020 to replace the 120PSB light bulbs with new LEDs and a new item of sockets. However, the licensee failed to complete an extent of condition review in a timely manner, appropriate for the safety significance of the issue, to properly classify and prioritize corrective actions associated with 120PSB light bulbs and socket causing inoperability of safety-related equipment (i.e., the remaining 120PSB lightbulbs with F series sockets for EDG A and B).

CRs 10009585 and 10009587: The equipment performance evaluation (CR 10009585) and common cause (CR 10009587) both concluded the most probable cause was an internal short within the 120PSB incandescent bulb resulting in a spurious lockout relay actuation that prevented equipment operation, due to an inadequate original plant circuit. Additionally, the licensee concluded actions taken in support of CR 2004-1024, CR 140271, and CR 140866 were ineffective.

Corrective Actions: The licensee removed the 120PSB incandescent bulbs from EDG A and B, reset the 186-1 and 186-2 lockout relays; upgraded to LEDs and replace the associated sockets with a new design; and perform an extent of condition evaluation.

Corrective Action References: CRs 10009585, 10009587, 10009590

Performance Assessment:

Performance Deficiency: The licensees failure to correct a condition adverse to quality associated with short circuits of 120PSB incandescent bulbs and their associated sockets causing inoperability of the EDG B was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure of the 120PSB incandescent bulb and its associated socket causing a short circuit that actuated the 186-2 lockout relay preventing the EDG B output breaker from closing, resulting in EDG B being declared inoperable.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, the finding was determined to be very low safety significance (Green) because it:

(1) was not a design deficiency,

(2) did not represent a loss of system and/or function,

(3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,

(4) did not represent a loss of the probabilistic assessment (PRA) function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

(5) did not represent a loss of a PRA system and/or function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

(6) did not result in the loss of a high safety-significant, nontechnical specification train.

Cross-Cutting Aspect: P.2 - Evaluation: The organization thoroughly evaluates issues to ensure that resolutions address causes and extent of conditions appropriate for their safety significance. Specifically, the licensee failed to complete an extent of condition in a timely manner, appropriate for the safety significance of the issue to properly classify and prioritize corrective actions associated with incandescent lightbulbs and associated F series sockets that could impact safety-related equipment (i.e., the remaining EDG A and B incandescent lightbulbs and associated F series sockets).

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, states, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to the above, between May 2004 to November 2021, the licensee failed to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformance are promptly corrected. Specifically, the licensee failed to correct a condition adverse to quality associated with 120PSB incandescent bulbs and their associated sockets short circuiting and causing inoperability of EDG B.

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

EXIT MEETINGS AND DEBRIEFS

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

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

On November 18, 2021, the inspectors presented the emergency plan changes and performance indicator verification inspection results to M. Dekat, Manager, Emergency Preparedness, and other members of the licensee staff.

On January 6, 2022, the inspectors presented the ISFSI preoperational exercises and Part 72 program inspection results to Mr. C. Reasoner, Chief Executive Officer and Chief Nuclear Officer, and other members of the licensee staff.

On January 13, 2022, the inspectors presented the integrated inspection results to Mr. B. Bayer, General Manager, Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60854 Procedures PTIP 3051-5.11c EOS-37PTH TC Handling and Fuel Loading 0

60854 Procedures PTIP 3051-5.11e DSC Insertion into HSM-MX 0

60854 Procedures PTIP 3051-5.11f DSC Retraction into Transfer Cask 0

60854 Procedures PTIP 3051-5.11g Guidance for ISFSI Equipment Malfunctions 0

60856 Calculations 108093-C-001 SSI Analysis 1

60856 Calculations 108093-C-002 ISFSI Pad Analysis and Design 1

60856 Calculations TN EOS01-0319 MX Transfer skid and SEFIRO Transfer Trailer System 0

stability evaluation for tornado wind, missile impact and

seismic loads

60856 Corrective Action Condition Reports 2021-285, 2020-241, 2021-278, 2021-279, 2021-288

Documents

60856 Engineering 30501-EE-006 Hazards Evaluation for the ISFSI 1

Evaluations

60856 Engineering LR 721042-098 NUHOMS MX-LC and RRT 1

Evaluations

60856 Procedures AP 26A-009 10 CFR 72.48 Reviews 0

60856 Procedures WCNOC-4 Report on Control of Heavy Loads, Lifting and Rigging 21

71111.04 Corrective Action Condition Report 10010040

Documents

71111.04 Drawings M-12EM01 Piping and Instrumentation Diagram High Pressure Coolant 46

Injection System

71111.04 Drawings M-12EP01 Piping and Instrumentation Diagram Accumulator Safety 17

Injection

71111.04 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 12

71111.04 Procedures AP 15C-004 Preparation, Review and Approval of Procedures, 55A

Instructions and Forms

71111.04 Procedures AP 26C-004 Operability Determination and Functionality Assessment 45

71111.04 Procedures SYS EP-200 Safety Injection Accumulator Operations 50

71111.05 Corrective Action Condition Reports 10000916, 10009970

Documents

71111.05 Corrective Action Condition Report 10010105

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

71111.05 Drawings E-13GK31 Schematic Diagram Fire Signal Isolation 6

71111.05 Drawings M-12GK04 Piping and Instrumentation Diagram Control Building HVAC 15

71111.05 Miscellaneous BAP-21-0396 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0397 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0398 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0399 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0440 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0441 Breach Authorization Permit

71111.05 Miscellaneous BAP-21-0444 Breach Authorization Permit

71111.05 Miscellaneous E-1F9905 Fire Hazard Analysis 11

71111.05 Miscellaneous WCRE-35 Boundary Matrix 8

71111.05 Procedures ALR KC-888 Fire Protection Panel KC-008 Alarm Response 32

71111.05 Procedures AP 10-100 Fire Protection Program 24

71111.05 Procedures AP 10-103 Fire Protection Impairment Control 37

71111.05 Procedures AP 10-104 Breach Authorization 39

71111.05 Procedures AP 10-106 Fire Preplan 21

71111.05 Procedures AP-109 Fire Protection Inspections 9

71111.05 Procedures OFN KC-016 Fire Response 51

71111.05 Procedures STN FP-402A Train A HALON System Checkout for KC-230 11

71111.05 Procedures STN FP-402B Train B HALON System Checkout for KC-230 11

71111.05 Procedures SYS GB-200 Chilled Water System Operation 41

71111.05 Procedures SYS GK-201 Mitigating Actions for Inoperable SKG05 Train 3A

71111.11Q Corrective Action Condition Report 10009813

Documents

71111.11Q Procedures AI 21-300 Flexible Power Operations 2

71111.12 Corrective Action Condition Reports 67122, 136146, 136778, 138215, 139226, 141273, 143729,

Documents 10005736, 10008456, 10008863, 10008874, 10009461,

10009463, 10009464, 10009465, 10009466, 10009619,

10009841, 10010238, 10010613

71111.12 Corrective Action Condition Report 10010430

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

71111.12 Drawings J-12AE12 Feedwater System Motor Driven Pump Control Logic 0

Diagram

71111.12 Drawings M-12AE01 Piping and Instrumentation Diagram Feedwater System 44

71111.12 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 32

System

71111.12 Engineering DCP 020161 Removal of Interlock to Motor Driven Feedwater Pump Motor 1

Changes Start

71111.12 Miscellaneous M-022-00001 Station Blackout Diesel Generator Kohler Instruction Manual W03

71111.12 Miscellaneous M-022-00012 SBO Diesel Generator Battery and 125 VDC Support W01

Equipment

71111.12 Miscellaneous M-022-00018 Station Blackout Diesel Operations and Maintenance Manual W01

71111.12 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 12

71111.12 Procedures AP 05-007 Determination of Safety Classification 15

71111.12 Procedures AP 05J-001 Quality Group (Augmented) Quality Program Requirements 5

71111.12 Procedures AP 23M-001 WCGS Maintenance Rule Program 13

71111.12 Procedures EMG C-0 Loss of All AC Power 45

71111.12 Procedures EMG ES-02 Reactor Trip Response 41

71111.12 Procedures EMG FR-H1 Response to Loss of Secondary Heat Sink 37

71111.12 Procedures GEN 00-005 Minimum Load to Hot Standby 95

71111.12 Procedures STN AE-007 Startup Main Feedwater Pump Operational Test 15

71111.12 Procedures SYS AE-122 Startup Main Feedwater Pump Startup 41

71111.12 Procedures SYS AE-200 Feedwater Preheating during Plant Startup and Shutdown 44

71111.12 Procedures SYS KU-124 SBO Generator Local or Manual Operations 7

71111.12 Work Orders WO 13-366996-000, 17-432438-000, 17-432438-003, 17-

2438-007, 21-475640-000

71111.13 Corrective Action Condition Reports 10009585, 10010040, 10010238

Documents

71111.13 Drawings E-13NE11 Schematic Diagram 4.16kV DG NE02 Feeder Breaker 20

2NB0211

71111.13 Miscellaneous BAP-21-0440 Breach Authorization Permit

71111.13 Miscellaneous PIR 1997-3174 Performance Improvement Request Review

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.13 Miscellaneous STS PE-004 Aux Building and Control Room Pressure Test as performed 10

on 11/20/1998

71111.13 Miscellaneous WCRE-35 Boundary Matrix 8

71111.13 Procedures ALR 00-023D DG NE2 Trouble 10

71111.13 Procedures AP 10-104 Breach Authorization 39

71111.13 Procedures SYS GB-200 Chilled Water System Operation 41

71111.13 Procedures SYS KJ-200 Inoperable Emergency Diesel 34A

71111.13 Work Orders WO 21-475280-000, 21-475496-000, 21-475640-000

71111.15 Corrective Action Condition Reports 025709, 031273, 073235, 10009660, 10009934, 10009945,

Documents 10010376, 10010460, 10009587

71111.15 Drawings E-13EG01D Schematic Diagram Component Cooling Water Pump D 5

71111.15 Drawings J-110-00212 Component Cooling Water System CCW Pumps B&D 0

Discharge Header Pressure

71111.15 Drawings M-018-00185 Electrical Schematic Diesel Gen. Control NE107 (NE106) W16

71111.15 Drawings M-12EG01 Piping and Instrumentation Diagram Component Cooling 26

Water System

71111.15 Drawings M-761-00072 Loop 1 Tavg and DT

71111.15 Drawings M-761-00077 Pressurizer Pressure

71111.15 Miscellaneous E-1F9910 Post Fire Shutdown Area Analysis 17

71111.15 Procedures ALR 00-054B CCW PMP B/D Press LO 8

71111.15 Procedures AP 26C-004 Operability Determination and Functionality Assessment 45

71111.15 Procedures AP 28-001 Operability Evaluations 27

71111.15 Procedures OFN EG-004 CCW System Malfunctions 19

71111.15 Procedures STN IC-458 Channel Calibration CCW Pump Discharge Pressure Loop 6A

EG PT-0078

71111.15 Procedures STS KJ-001B Integrated D/G and Safeguards Actuation Test - Train B 67

71111.15 Work Orders WO 21-475453-000

71111.19 Corrective Action Condition Reports 10009065, 10010040, 10010141, 10010159, 10010238

Documents

71111.19 Miscellaneous M-622.1A-0089 SGK04A, SGK04B, SGK05A, and SGK05A Air Conditioning W18

Condensers

71111.19 Procedures 16E-002 Post Maintenance Testing Development 21A

71111.19 Procedures MPE GK-003 Control Room and Class 1E A/C Units Preventative 7

Inspection Type Designation Description or Title Revision or

Procedure Date

Maintenance Activity

71111.19 Procedures MPE GK-004 GK Unit Preparation for Work 11A

71111.19 Procedures SYS GK-123 Control Building A/C Units Startup and Shutdown 36

71111.19 Work Orders WO 21-475496-000, 21-475496-009, 21-475640-000

71114.04 Corrective Action Condition Reports 10010666, 10010667, 10010671

Documents

Resulting from

Inspection

71114.04 Miscellaneous E-Plan Screening: EPP 06-006, Protective Action 06/09/2021

Recommendations, Rev. 10A

71114.04 Miscellaneous E-Plan Screening: EPP 06-007, Emergency Notifications, 07/29/2021

Rev 27

71114.04 Miscellaneous E-Plan Effectiveness Evaluation: EPP 06-007, Emergency 07/29/2021

Notifications, Rev. 27

71114.04 Miscellaneous E-Plan Effectiveness Evaluation: EPP 06-019, Alert and 05/25/2021

Notification System Sirens, Rev. 10 (Eliminated/Superseded)

71114.04 Miscellaneous E-Plan Screening: EPP 06-019, Alert and Notification 03/31/2021

System Sirens, Rev. 10 (Eliminated/Superseded)

71114.04 Miscellaneous E-Plan Screening: EPP 06-012, Dose Assessment, Rev. 17B 05/20/2021

71114.04 Miscellaneous E-Plan Screening: AP 06-002, Radiological Emergency 07/12/2021

Response Plan (RERP), Rev 22

71114.04 Miscellaneous E-Plan Effectiveness Evaluation: AP 06-002, Radiological 06/07/2021

Emergency Response Plan (RERP), Rev 22

71114.04 Miscellaneous E-Plan Screening: APF 06-002-03, EAL Classification Matrix, 05/26/2021

Rev. 1

71114.04 Miscellaneous E-Plan Effectiveness Evaluation: APF 06-002-03, EAL 06/14/2021

Classification Matrix, Rev. 1

71114.04 Miscellaneous E-Plan Screening: APF 06-002-02, Emergency Action Levels 05/26/2021

Technical Bases, Rev. 1

71114.04 Miscellaneous E-Plan Effectiveness Evaluation: APF 06-002-02, 06/14/2021

Emergency Action Levels Technical Bases, Rev. 1

71114.04 Procedures AI 26A-003 Regulatory Evaluations (Other Than 10 CFR 50.59) 16, 17

71124.02 ALARA Plans Wolf Creek ALARA 5-Year Plan 2017-2021 04/01/2021

71124.02 ALARA Plans Wolf Creek ALARA Long Range Exposure/Source Term 02/01/2015

Inspection Type Designation Description or Title Revision or

Procedure Date

Reduction Plan (2015-2019)

71124.02 ALARA Plans RWP 191000 Radiation Protection Rover Coverage ALARA Review

Package

71124.02 ALARA Plans RWP 194207 Reactor Coolant Pump Team & Preventative Maintenance

ALARA Review Package

71124.02 ALARA Plans RWP 194482 Remove/Install Canopy Seal Weld Clamps ALARA Review

Package

71124.02 ALARA Plans RWP 194483 Reactor Vessel Head Reassembly (to include canopy seal

clamps) ALARA Review Package

71124.02 ALARA Plans RWP 213057 Under Reactor Head Entries for Electric Discharge

Machining ALARA Review Package

71124.02 ALARA Plans RWP 213220 Primary Side Steam Generator Eddy Current Testing and

Zero Entry Nozzle Dam ALARA Review Package

71124.02 ALARA Plans RWP 214199 Secondary Side Steam Generator Foreign Object

Search/Retrieval and Visual Inspections ALARA Review

Package

71124.02 ALARA Plans RWP 214200 Secondary Side Steam Generator Sludge Lance ALARA

Review Package

71124.02 ALARA Plans RWP 216020 Reactor Vessel Head Lift Preparation and Post Head Set

Work Activities ALARA Review Package

71124.02 Corrective Action Condition Reports 00131535, 00134905, 00136925, 00137267, 00138067,

Documents 00138968, 00139463, 00140656, 00140657, 00140676,

00140681, 00141484, 00141485, 00141486, 00144502,

10001089, 10003789, 10004210

71124.02 Procedures AP 25A-300 RWP Program 26

71124.02 Procedures AP 25A-401 ALARA Program 28

71124.02 Procedures AP 25A-410 ALARA Committee 25

71124.02 Procedures RPP 02-105 Radiation Work Permits 50

71124.02 Radiation M-20210127-5 Auxiliary-2000-1306 01/27/2021

Surveys

71124.02 Radiation M-20210405-22 RF-24 EPRI Survey 04/05/2021

Surveys

71124.02 Self-Assessments Refuel 24 Outage Report 07/07/2021

71124.02 Self-Assessments Refuel 23 Outage Report 01/27/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.02 Self-Assessments 20-01-RP/PC Quality Assurance Audit Report - QA Radiological Protection 03/02/2020

& Process Control Programs Audit

71124.02 Self-Assessments Condition Report Self-Assessment for NRC Inspection 71124 Attachment 02

(CR) #00146305

71124.04 Corrective Action Condition Reports 00136261, 00137866, 00138625, 00138806, 00140629,

Documents 00140663, 00140674, 00140675, 00144019, 00144020,

10004384, 10004684, 10004685, 10006933, 10007294,

10009578

71124.04 Miscellaneous 2019 DAC-Hour Summary 10/16/2019

71124.04 Miscellaneous 2020 DAC-Hour Summary 09/16/2020

71124.04 Miscellaneous 2021 DAC-Hour Summary 04/17/2021

71124.04 Miscellaneous Calibration Documentation WBC-200-GEM10 High Purity 02/25/2021

Germanium Based Chair

71124.04 Miscellaneous 2019 Wolf Creek Multi-Packs per Person Log 2019

71124.04 Miscellaneous 2021 Wolf Creek Multi-Packs per Person Log 2021

71124.04 Miscellaneous Wolf Creek ALARA 5-Year Plan 2017-2021 04/01/2021

71124.04 Miscellaneous Wolf Creek Dose Excellence Plan 2017-2021 07/27/2017

71124.04 Miscellaneous List of Positive Whole Body Counts from 3/11/2019 to 09/01/2021

9/1/2021

71124.04 Miscellaneous WO 537181 WCNOC 10 CFR Part 61 Analysis 04/05/2021

71124.04 Procedures AP 25A-001 Radiation Protection Manual 19

71124.04 Procedures AP 25B-100 Radiation Worker Guidelines 54A

71124.04 Procedures AP 25B-400 Planned Special Exposures 3C

71124.04 Procedures RPP 02-305 Personnel Surveys/Decontamination 30

71124.04 Procedures RPP 03-121 Determination of Neutron Dose 8

71124.04 Procedures RPP 03-205 DAC-Hour Tracking 17A

71124.04 Procedures RPP 03-210 Internal Exposure Calculations and Evaluations 17B

71124.04 Procedures RPP 03-406 Radiation Protection Dosimetry/Records 16

71124.04 Procedures RPP 05-707 Operation of Whole Body Counter 10B

71124.04 Radiation Work RWP 192001 Mechanical Maintenance Welding Department RWP for 0

Permits (RWPs) Work Activities by Mechanical Maintenance Supervision

71124.04 Radiation Work RWP 200061 Fuel Building Transfer Canal Entry for Repairs/Inspection 0

Permits (RWPs) and Decon of Fuel Building Transfer System

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.04 Radiation Work RWP 214486 RWP to be used for CO2 Blasting Decon of the RX Head in 0

Permits (RWPs) CTMT and Associated Activities in the Fuel Building

71124.04 Self-Assessments Self-Assessment for NRC Inspection 71124, Attachment 04 09/07/2021

71124.04 Self-Assessments Quick Hit 2017- NRC Inspection Procedure 71124.04, Occupational Dose 07/12/2017

1505 Assessment, and NRC 71124.02, Occupational ALARA

Planning and Controls

71124.04 Self-Assessments Quick Hit 2019- NRC Inspection Procedure 71124.04, Occupational Dose 02/27/2019

1801 Assessment

71151 Corrective Action Condition Reports 10001964, 10001986, 10001992, 10006572, 10008518,

Documents 10009546, 10009731

71151 Corrective Action Condition Reports 10010664, 10010665, 10010673

Documents

Resulting from

Inspection

71151 Miscellaneous DEP PI Evaluation - Annual Exam Session 07/08/2020

LR9490001/Rev 000 (Hawes/Hamman)

71151 Miscellaneous DEP PI Evaluation - Annual Exam Session 07/15/2020

LR9490001/Rev 000 (Faircloth/Dekat)

71151 Miscellaneous DEP PI Evaluation - LOR Session LR4640001/Rev 005 08/19/2020

(Pitt/Strahm)

71151 Miscellaneous DEP PI Evaluation - Table Top Series #1 10/28/2020

(GE1135662/Rev 004), DLA#1 - DLA#5

71151 Miscellaneous DEP PI Evaluation - Table Top Series #3 12/02/2020

(GE1135662/Rev 004), DLA#1 - DLA#4

71151 Miscellaneous DEP PI Evaluation - Drill 21-SA-02 (GE1135656/Rev 000), 03/02/2021

Team A/C

71151 Miscellaneous ERO Drill Participation Tracking Data Sheets 3Q/2020 -

3Q/2021

71151 Miscellaneous DEP PI Evaluation - Drill 21-SA-02 (GE1135656/Rev 000), 06/15/2021

Team D/A

71151 Miscellaneous DEP PI Evaluation - LOR Session LR4422801/Rev 003 06/09/2021

(Hawes/Perry)

71151 Miscellaneous DEP PI Evaluation - LOR Session LR4422801/Rev 003 06/16/2021

(Hamman/Turner)

Inspection Type Designation Description or Title Revision or

Procedure Date

71151 Miscellaneous DEP PI Evaluation - LOR Session LR4422801/Rev 003 06/23/2021

(Rholfing/Payne)

71151 Miscellaneous DEP PI Evaluation - 2021 Table Top Series II 06/16/2021

(GE1135662/Rev 004), Team D, DLA#1 - DLA#4

71151 Miscellaneous DEP PI Evaluation - Annual Exam Session 06/24/2020

LR9490001/Rev 000 (Greenfield/Grigsby)

71151 Miscellaneous DEP PI Evaluation - Annual Exam Session 07/22/2020

LR9490001/Rev 000 (Rohlfing/Payne)

71151 Miscellaneous DEP PI Evaluation - Annual Exam Session 06/10/2020

LR9490001/Rev 000 (Martinson/Laubner)

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

71151 Procedures AI 26A-004 Emergency Planning Performance Indicators 9

71152 Corrective Action Condition Reports 123660, 135873, 139820, 140271, 140353, 140866, 141862,

Documents 142096, 144072, 10000838, 10001040, 10001612,

10003119, 10007096, 10007438, 10007572, 10007814,

10009585, 10009587, 10009590, 10009801, 10009807,

10010305, 10010306

71152 Corrective Action Condition Reports 10010923, 10010924, 10010925, 10010926

Documents

Resulting from

Inspection

71152 Drawings E-13NE11 Schematic Diagram 4.16kV DG NE02 Feeder Breaker 20

2NB0211

71152 Engineering CP 20403 LED Replacement for Incandescent Lamps 0

Changes

71152 Engineering EC 020406 Copper Sensing Line Replacement 3

Changes

71152 Miscellaneous M-622.1A-00089 Instruction Manual for SGK04A, SGK04B, SGK05A, and W18

SGK05B Air Conditioning Condensers

71152 Miscellaneous SCA-21-0009 Sensing Line Protective Plate SGK04A/B, SGK05A/B 0

71152 Procedures AI 28A-100 Condition Report Resolution 22

71152 Procedures AP 28A-100 Corrective Action Program 26A

71152 Procedures INC S-0504 Tube Fitting and Installation Standard and Practices 7

71152 Work Orders WO 20-462340-001, 20-462739-027, 20-462739-035, 21-

Inspection Type Designation Description or Title Revision or

Procedure Date

475367-000, 21-475367-001

71153 Corrective Action Condition Reports 143097, 10008456, 10008863, 10008874, 10010417

Documents

71153 Procedures AI 28A-010 Screening Condition Reports 36

71153 Procedures AI 28A-102 Root Cause Analysis 3

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2021004

AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079

/2021002 DATE January 19, 2022