IR 05000482/2021004
| 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, 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:
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
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 Aspect Report Section Mitigating Systems Green FIN 05000482/2021004-01 Open/Closed
[H.13] -
Consistent Process 71111.12 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 Aspect Report Section Mitigating Systems Green NCV 05000482/2021004-02 Open/Closed
[P.2] -
Evaluation 71152 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 due to Main Feedwater Valve Failure Caused Automatic Reactor Trip 71153 Closed
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.
REACTOR SAFETY
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.
RADIATION SAFETY
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:
- (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 Aspect Report Section Mitigating Systems Green FIN 05000482/2021004-01 Open/Closed
[H.13] -
Consistent Process 71111.12 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 Aspect Report Section Mitigating Systems Green NCV 05000482/2021004-02 Open/Closed
[P.2] -
Evaluation 71152 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
Procedure
Type
Designation
Description or Title
Revision or
Date
60854
Procedures
PTIP 3051-5.11c
EOS-37PTH TC Handling and Fuel Loading
60854
Procedures
PTIP 3051-5.11e
DSC Insertion into HSM-MX
60854
Procedures
PTIP 3051-5.11f
DSC Retraction into Transfer Cask
60854
Procedures
PTIP 3051-5.11g
Guidance for ISFSI Equipment Malfunctions
60856
Calculations
108093-C-001
SSI Analysis
60856
Calculations
108093-C-002
ISFSI Pad Analysis and Design
60856
Calculations
TN EOS01-0319
MX Transfer skid and SEFIRO Transfer Trailer System
stability evaluation for tornado wind, missile impact and
seismic loads
60856
Corrective Action
Documents
Condition Reports21-285, 2020-241, 2021-278, 2021-279, 2021-288
60856
Engineering
Evaluations
30501-EE-006
Hazards Evaluation for the ISFSI
60856
Engineering
Evaluations
LR 721042-098
NUHOMS MX-LC and RRT
60856
Procedures
CFR 72.48 Reviews
60856
Procedures
WCNOC-4
Report on Control of Heavy Loads, Lifting and Rigging
Corrective Action
Documents
Condition Report
10010040
Drawings
M-12EM01
Piping and Instrumentation Diagram High Pressure Coolant
Injection System
Drawings
M-12EP01
Piping and Instrumentation Diagram Accumulator Safety
Injection
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Procedures
Preparation, Review and Approval of Procedures,
Instructions and Forms
55A
Procedures
Operability Determination and Functionality Assessment
Procedures
SYS EP-200
Safety Injection Accumulator Operations
Corrective Action
Documents
Condition Reports
10000916, 10009970
Corrective Action
Documents
Condition Report
10010105
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Drawings
E-13GK31
Schematic Diagram Fire Signal Isolation
Drawings
M-12GK04
Piping and Instrumentation Diagram Control Building HVAC
Miscellaneous
BAP-21-0396
Breach Authorization Permit
Miscellaneous
BAP-21-0397
Breach Authorization Permit
Miscellaneous
BAP-21-0398
Breach Authorization Permit
Miscellaneous
BAP-21-0399
Breach Authorization Permit
Miscellaneous
BAP-21-0440
Breach Authorization Permit
Miscellaneous
BAP-21-0441
Breach Authorization Permit
Miscellaneous
BAP-21-0444
Breach Authorization Permit
Miscellaneous
E-1F9905
Fire Hazard Analysis
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
ALR KC-888
Fire Protection Panel KC-008 Alarm Response
Procedures
AP 10-100
Procedures
AP 10-103
Fire Protection Impairment Control
Procedures
AP 10-104
Breach Authorization
Procedures
AP 10-106
Fire Preplan
Procedures
AP-109
Fire Protection Inspections
Procedures
OFN KC-016
Fire Response
Procedures
STN FP-402A
Train A HALON System Checkout for KC-230
Procedures
STN FP-402B
Train B HALON System Checkout for KC-230
Procedures
SYS GB-200
Chilled Water System Operation
Procedures
SYS GK-201
Mitigating Actions for Inoperable SKG05 Train
3A
Corrective Action
Documents
Condition Report
10009813
Procedures
AI 21-300
Flexible Power Operations
Corrective Action
Documents
Condition Reports
67122, 136146, 136778, 138215, 139226, 141273, 143729,
10005736, 10008456, 10008863, 10008874, 10009461,
10009463, 10009464, 10009465, 10009466, 10009619,
10009841, 10010238, 10010613
Corrective Action
Documents
Condition Report
10010430
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Drawings
J-12AE12
Feedwater System Motor Driven Pump Control Logic
Diagram
Drawings
M-12AE01
Piping and Instrumentation Diagram Feedwater System
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Engineering
Changes
DCP 020161
Removal of Interlock to Motor Driven Feedwater Pump Motor
Start
Miscellaneous
M-022-00001
Station Blackout Diesel Generator Kohler Instruction Manual
W03
Miscellaneous
M-022-00012
SBO Diesel Generator Battery and 125 VDC Support
Equipment
W01
Miscellaneous
M-022-00018
Station Blackout Diesel Operations and Maintenance Manual
W01
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Procedures
AP 05-007
Determination of Safety Classification
Procedures
Quality Group (Augmented) Quality Program Requirements
Procedures
Procedures
EMG C-0
Loss of All AC Power
Procedures
EMG ES-02
Reactor Trip Response
Procedures
EMG FR-H1
Response to Loss of Secondary Heat Sink
Procedures
GEN 00-005
Minimum Load to Hot Standby
Procedures
STN AE-007
Startup Main Feedwater Pump Operational Test
Procedures
SYS AE-122
Startup Main Feedwater Pump Startup
Procedures
SYS AE-200
Feedwater Preheating during Plant Startup and Shutdown
Procedures
SYS KU-124
SBO Generator Local or Manual Operations
Work Orders
13-366996-000, 17-432438-000, 17-432438-003, 17-
2438-007, 21-475640-000
Corrective Action
Documents
Condition Reports
10009585, 10010040, 10010238
Drawings
E-13NE11
Schematic Diagram 4.16kV DG NE02 Feeder Breaker
2NB0211
Miscellaneous
BAP-21-0440
Breach Authorization Permit
Miscellaneous
PIR 1997-3174
Performance Improvement Request Review
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
STS PE-004
Aux Building and Control Room Pressure Test as performed
on 11/20/1998
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
ALR 00-023D
DG NE2 Trouble
Procedures
AP 10-104
Breach Authorization
Procedures
SYS GB-200
Chilled Water System Operation
Procedures
SYS KJ-200
Inoperable Emergency Diesel
34A
Work Orders
21-475280-000, 21-475496-000, 21-475640-000
Corrective Action
Documents
Condition Reports
25709, 031273, 073235, 10009660, 10009934, 10009945,
10010376, 10010460, 10009587
Drawings
E-13EG01D
Schematic Diagram Component Cooling Water Pump D
Drawings
Component Cooling Water System CCW Pumps B&D
Discharge Header Pressure
Drawings
M-018-00185
Electrical Schematic Diesel Gen. Control NE107 (NE106)
W16
Drawings
M-12EG01
Piping and Instrumentation Diagram Component Cooling
Water System
Drawings
M-761-00072
Loop 1 Tavg and DT
Drawings
M-761-00077
Pressurizer Pressure
Miscellaneous
E-1F9910
Post Fire Shutdown Area Analysis
Procedures
ALR 00-054B
Procedures
Operability Determination and Functionality Assessment
Procedures
AP 28-001
Operability Evaluations
Procedures
OFN EG-004
CCW System Malfunctions
Procedures
STN IC-458
Channel Calibration CCW Pump Discharge Pressure Loop
EG PT-0078
6A
Procedures
STS KJ-001B
Integrated D/G and Safeguards Actuation Test - Train B
Work Orders
21-475453-000
Corrective Action
Documents
Condition Reports
10009065, 10010040, 10010141, 10010159, 10010238
Miscellaneous
M-622.1A-0089
SGK04A, SGK04B, SGK05A, and SGK05A Air Conditioning
Condensers
W18
Procedures
Post Maintenance Testing Development
21A
Procedures
MPE GK-003
Control Room and Class 1E A/C Units Preventative
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Maintenance Activity
Procedures
MPE GK-004
GK Unit Preparation for Work
11A
Procedures
SYS GK-123
Control Building A/C Units Startup and Shutdown
Work Orders
21-475496-000, 21-475496-009, 21-475640-000
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10010666, 10010667, 10010671
Miscellaneous
E-Plan Screening: EPP 06-006, Protective Action
Recommendations, Rev. 10A
06/09/2021
Miscellaneous
E-Plan Screening: EPP 06-007, Emergency Notifications,
Rev 27
07/29/2021
Miscellaneous
E-Plan Effectiveness Evaluation: EPP 06-007, Emergency
Notifications, Rev. 27
07/29/2021
Miscellaneous
E-Plan Effectiveness Evaluation: EPP 06-019, Alert and
Notification System Sirens, Rev. 10 (Eliminated/Superseded)
05/25/2021
Miscellaneous
E-Plan Screening: EPP 06-019, Alert and Notification
System Sirens, Rev. 10 (Eliminated/Superseded)
03/31/2021
Miscellaneous
E-Plan Screening: EPP 06-012, Dose Assessment, Rev. 17B 05/20/2021
Miscellaneous
E-Plan Screening: AP 06-002, Radiological Emergency
Response Plan (RERP), Rev 22
07/12/2021
Miscellaneous
E-Plan Effectiveness Evaluation: AP 06-002, Radiological
Emergency Response Plan (RERP), Rev 22
06/07/2021
Miscellaneous
E-Plan Screening: APF 06-002-03, EAL Classification Matrix,
Rev. 1
05/26/2021
Miscellaneous
E-Plan Effectiveness Evaluation: APF 06-002-03, EAL
Classification Matrix, Rev. 1
06/14/2021
Miscellaneous
E-Plan Screening: APF 06-002-02, Emergency Action Levels
Technical Bases, Rev. 1
05/26/2021
Miscellaneous
E-Plan Effectiveness Evaluation: APF 06-002-02,
Emergency Action Levels Technical Bases, Rev. 1
06/14/2021
Procedures
AI 26A-003
Regulatory Evaluations (Other Than 10 CFR 50.59)
16, 17
ALARA Plans
Wolf Creek ALARA 5-Year Plan 2017-2021
04/01/2021
ALARA Plans
Wolf Creek ALARA Long Range Exposure/Source Term
2/01/2015
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Reduction Plan (2015-2019)
ALARA Plans
RWP 191000
Radiation Protection Rover Coverage ALARA Review
Package
ALARA Plans
RWP 194207
Reactor Coolant Pump Team & Preventative Maintenance
ALARA Review Package
ALARA Plans
RWP 194482
Remove/Install Canopy Seal Weld Clamps ALARA Review
Package
ALARA Plans
RWP 194483
Reactor Vessel Head Reassembly (to include canopy seal
clamps) ALARA Review Package
ALARA Plans
RWP 213057
Under Reactor Head Entries for Electric Discharge
Machining ALARA Review Package
ALARA Plans
RWP 213220
Primary Side Steam Generator Eddy Current Testing and
Zero Entry Nozzle Dam ALARA Review Package
ALARA Plans
RWP 214199
Secondary Side Steam Generator Foreign Object
Search/Retrieval and Visual Inspections ALARA Review
Package
ALARA Plans
RWP 214200
Secondary Side Steam Generator Sludge Lance ALARA
Review Package
ALARA Plans
RWP 216020
Reactor Vessel Head Lift Preparation and Post Head Set
Work Activities ALARA Review Package
Corrective Action
Documents
Condition Reports 00131535, 00134905, 00136925, 00137267, 00138067,
00138968, 00139463, 00140656, 00140657, 00140676,
00140681, 00141484, 00141485, 00141486, 00144502,
10001089, 10003789, 10004210
Procedures
RWP Program
Procedures
ALARA Program
Procedures
ALARA Committee
Procedures
RPP 02-105
Radiation Work Permits
Radiation
Surveys
M-20210127-5
Auxiliary-2000-1306
01/27/2021
Radiation
Surveys
M-20210405-22
RF-24 EPRI Survey
04/05/2021
Self-Assessments
Refuel 24 Outage Report
07/07/2021
Self-Assessments
Refuel 23 Outage Report
01/27/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessments 20-01-RP/PC
Quality Assurance Audit Report - QA Radiological Protection
& Process Control Programs Audit
03/02/2020
Self-Assessments Condition Report
(CR) #00146305
Self-Assessment for NRC Inspection 71124 Attachment 02
Corrective Action
Documents
Condition Reports 00136261, 00137866, 00138625, 00138806, 00140629,
00140663, 00140674, 00140675, 00144019, 00144020,
10004384, 10004684, 10004685, 10006933, 10007294,
10009578
Miscellaneous
2019 DAC-Hour Summary
10/16/2019
Miscellaneous
20 DAC-Hour Summary
09/16/2020
Miscellaneous
21 DAC-Hour Summary
04/17/2021
Miscellaneous
Calibration Documentation WBC-200-GEM10 High Purity
Germanium Based Chair
2/25/2021
Miscellaneous
2019 Wolf Creek Multi-Packs per Person Log
2019
Miscellaneous
21 Wolf Creek Multi-Packs per Person Log
21
Miscellaneous
Wolf Creek ALARA 5-Year Plan 2017-2021
04/01/2021
Miscellaneous
Wolf Creek Dose Excellence Plan 2017-2021
07/27/2017
Miscellaneous
List of Positive Whole Body Counts from 3/11/2019 to
9/1/2021
09/01/2021
Miscellaneous
WCNOC 10 CFR Part 61 Analysis
04/05/2021
Procedures
Radiation Protection Manual
Procedures
Radiation Worker Guidelines
54A
Procedures
Planned Special Exposures
3C
Procedures
RPP 02-305
Personnel Surveys/Decontamination
Procedures
RPP 03-121
Determination of Neutron Dose
Procedures
RPP 03-205
DAC-Hour Tracking
17A
Procedures
RPP 03-210
Internal Exposure Calculations and Evaluations
17B
Procedures
RPP 03-406
Radiation Protection Dosimetry/Records
Procedures
RPP 05-707
Operation of Whole Body Counter
10B
Radiation Work
Permits (RWPs)
RWP 192001
Mechanical Maintenance Welding Department RWP for
Work Activities by Mechanical Maintenance Supervision
Radiation Work
Permits (RWPs)
RWP 200061
Fuel Building Transfer Canal Entry for Repairs/Inspection
and Decon of Fuel Building Transfer System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Work
Permits (RWPs)
RWP 214486
RWP to be used for CO2 Blasting Decon of the RX Head in
CTMT and Associated Activities in the Fuel Building
Self-Assessments
Self-Assessment for NRC Inspection 71124, Attachment 04
09/07/2021
Self-Assessments Quick Hit 2017-
1505
NRC Inspection Procedure 71124.04, Occupational Dose
Assessment, and NRC 71124.02, Occupational ALARA
Planning and Controls
07/12/2017
Self-Assessments Quick Hit 2019-
1801
NRC Inspection Procedure 71124.04, Occupational Dose
Assessment
2/27/2019
71151
Corrective Action
Documents
Condition Reports 10001964, 10001986, 10001992, 10006572, 10008518,
10009546, 10009731
71151
Corrective Action
Documents
Resulting from
Inspection
Condition Reports 10010664, 10010665, 10010673
71151
Miscellaneous
DEP PI Evaluation - Annual Exam Session
LR9490001/Rev 000 (Hawes/Hamman)
07/08/2020
71151
Miscellaneous
DEP PI Evaluation - Annual Exam Session
LR9490001/Rev 000 (Faircloth/Dekat)
07/15/2020
71151
Miscellaneous
DEP PI Evaluation - LOR Session LR4640001/Rev 005
(Pitt/Strahm)
08/19/2020
71151
Miscellaneous
DEP PI Evaluation - Table Top Series #1
(GE1135662/Rev 004), DLA#1 - DLA#5
10/28/2020
71151
Miscellaneous
DEP PI Evaluation - Table Top Series #3
(GE1135662/Rev 004), DLA#1 - DLA#4
2/02/2020
71151
Miscellaneous
DEP PI Evaluation - Drill 21-SA-02 (GE1135656/Rev 000),
Team A/C
03/02/2021
71151
Miscellaneous
ERO Drill Participation Tracking Data Sheets
3Q/2020 -
3Q/2021
71151
Miscellaneous
DEP PI Evaluation - Drill 21-SA-02 (GE1135656/Rev 000),
Team D/A
06/15/2021
71151
Miscellaneous
DEP PI Evaluation - LOR Session LR4422801/Rev 003
(Hawes/Perry)
06/09/2021
71151
Miscellaneous
DEP PI Evaluation - LOR Session LR4422801/Rev 003
(Hamman/Turner)
06/16/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Miscellaneous
DEP PI Evaluation - LOR Session LR4422801/Rev 003
(Rholfing/Payne)
06/23/2021
71151
Miscellaneous
DEP PI Evaluation - 2021 Table Top Series II
(GE1135662/Rev 004), Team D, DLA#1 - DLA#4
06/16/2021
71151
Miscellaneous
DEP PI Evaluation - Annual Exam Session
LR9490001/Rev 000 (Greenfield/Grigsby)
06/24/2020
71151
Miscellaneous
DEP PI Evaluation - Annual Exam Session
LR9490001/Rev 000 (Rohlfing/Payne)
07/22/2020
71151
Miscellaneous
DEP PI Evaluation - Annual Exam Session
LR9490001/Rev 000 (Martinson/Laubner)
06/10/2020
71151
Miscellaneous
WCNOC-163
Mitigating System Performance Index Basis Document
71151
Procedures
AI 26A-004
Emergency Planning Performance Indicators
Corrective Action
Documents
Condition Reports
23660, 135873, 139820, 140271, 140353, 140866, 141862,
2096, 144072, 10000838, 10001040, 10001612,
10003119, 10007096, 10007438, 10007572, 10007814,
10009585, 10009587, 10009590, 10009801, 10009807,
10010305, 10010306
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10010923, 10010924, 10010925, 10010926
Drawings
E-13NE11
Schematic Diagram 4.16kV DG NE02 Feeder Breaker
2NB0211
Engineering
Changes
CP 20403
LED Replacement for Incandescent Lamps
Engineering
Changes
Copper Sensing Line Replacement
Miscellaneous
M-622.1A-00089
Instruction Manual for SGK04A, SGK04B, SGK05A, and
SGK05B Air Conditioning Condensers
W18
Miscellaneous
SCA-21-0009
Sensing Line Protective Plate SGK04A/B, SGK05A/B
Procedures
AI 28A-100
Condition Report Resolution
Procedures
Corrective Action Program
26A
Procedures
INC S-0504
Tube Fitting and Installation Standard and Practices
Work Orders
20-462340-001, 20-462739-027, 20-462739-035, 21-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
475367-000, 21-475367-001
Corrective Action
Documents
Condition Reports
143097, 10008456, 10008863, 10008874, 10010417
Procedures
AI 28A-010
Screening Condition Reports
Procedures
AI 28A-102
Root Cause Analysis
GW
JE
HS
MH
FR
HG
VG
DP
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2021004
AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079
DATE
/2021002
January 19, 2022