IR 05000482/2022004

Integrated Inspection Report 05000482/2022004

ML23011A089
Person / Time
Site:	Wolf Creek
Issue date:	01/17/2023
From:	Greg Werner NRC/RGN-IV/DORS/PBB
To:	Reasoner C Wolf Creek
Werner G
References
IR 2022004
Download: ML23011A089 (35)

Text

January 17, 2023

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2022004

Dear Cleve Reasoner:

On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On January 10, 2023, the NRC inspectors discussed the results of this inspection with Jaime McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding 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.

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 Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket Number: 05000482

License Number: NPF-42

Report Number: 05000482/2022004

Licensee: Wolf Creek Nuclear Operating Corporation

Facility: Wolf Creek Generating Station

Location: Burlington, KS

Inspection Dates: October 1 to December 31, 2022

Inspectors: R. Azua, Senior Reactor Inspector B. Baca, Health Physicist C. Henderson, Senior Resident Inspector J. Melfi, Project Engineer J. O'Donnell, Senior Health Physicist J. Vera, Resident Inspector

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

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Wolf Creek Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Failure to Perform Air flow Testing for Safety-Related Safety Injection Pump B Room Cooler (SGL09B)

Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.12 Systems NCV 05000482/2022004-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion XI, Test Control, for the licensees failure to establish testing requirements for the safety-related safety injection pump B room cooler to measure air flow, which resulted in the licensing failing to identify fan belt glazing and slippage resulted in degraded air flow and required belt replacement.

Additional Tracking Items

None.

PLANT STATUS

Wolf Creek Generating Station began the inspection period at full power. On October 6, 2022, the unit was shut down to begin refueling outage 25. On November 19, 2022, the unit commenced reactor startup, and the reactor was made critical. The unit returned to full power on November 23, 2022, where it remained for the rest of the reporting period.

INSPECTION SCOPES

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

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather of a wind advisory for Coffey County Kansas which consisted of winds from 25 to 30 miles per hour (mph) with gusts of 45 mph. This consisted of conducting walkdowns for the switchyard, startup transformer, and train B engineered safety feature transformer on October 23, 2022.

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 A alternate offsite circuit through switchyard transformers 8 and 10 to safety-related 4160 V bus NB01 on October 21, 2022

(2) train A offsite circuit through switchyard transformers 9 and 11 to safety-related 4160 V bus NB01 on November 29, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

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

(1) reactor building cable tray area, elevation 2047-6, fire area RB-5, on October 6, 2022

(2) reactor building south electrical penetration area, elevation 2026-0, fire area reactor building 4, on October 13, 2022

(3) train B essential service water (ESW) pump room hot work, fire area ESWB, on October 21, 2022

(4) reactor building north electrical penetration area, elevation 2026-0, fire area reactor building 3, on October 26, 2022

(5) reactor building within the primary shield wall, fire area reactor building-11, on October 26, 2022

(6) radiological controlled area yard missed fire watch, fire area refueling water storage tank, on December 2, 2022

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 17 to November 22, 2022:

03.01.a - Nondestructive Examination and Welding Activities ultrasonic examination chemical volume control system, BG-02-F070, reference drawing M-189-50 ultrasonic examination chemical volume control system, BG-02-FW334, reference drawing M-189-50 ultrasonic examination chemical volume control system, BG-02-S040-A, reference drawing M-189-50 ultrasonic examination chemical volume control system, BG-02-S046-B, reference drawing M-189-50 ultrasonic examination of steam generator to main steam weld EBB01A-16-w, reference drawing M-189-50-ISI-EBB01A sheet 1 magnetic examination of steam generator to main steam weld EBB01A-16-w, reference drawing M-189-50-ISI-EBB01A sheet 1 visual examination of the reactor vessel head (RBB01), prompted by the identification of boric acid on the head dye penetrant examination reactor vessel head, penetration #19, canopy seal weld (IAW QCP-20-501)weld packages reviewed: reviewed the licensee actions to install accumulator loop 1 and safety injection loop 3 check valves (BB8948A; BB8949C),following the inclusion of cold springing effects when removing the previously installed check valves. This involved reviewing vendor analyses of applied forces to align the pipes for valve installation.

03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities The inspector reviewed the nondestructive examination report for the reactor vessel upper head penetration examination activities which consisted of a visual examination, and subsequent ultrasonic examination of selected control rod drive mechanism nozzles, which were performed to determine the source of identified boric acid on the reactor vessel head. No leakage points were identified on the reactor vessel upper head.

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities The inspector reviewed the following documents associated with boric acid leaks and evaluations: condition report (CR) 10018557, CR 10018704, CR 10018949, CR 10018711.

Problem Identification and Resolution The inspector reviewed 10 CRs associated with inservice and operating experience issues. No findings or violations of more than minor significance were identified.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during reactor shutdown for refueling outage 25 on October 5, 2022.

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

(1) The inspectors observed and evaluated reactor startup just-in-time training on November 7, 2022.

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) assessment of 10 CFR 50.63(a)(3) on December 13, 2022

(2) train B safety injection room cooler degraded air flow on November 30, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) the 345 kV east bus de-energized for transformer 9 and 11 installation with trains A and B safety-related 4160 V bus from engineering safety feature transformer 2 on October 7, 2022

(2) shutdown safety risk including spent fuel pool cooling and alternate spent fuel pool cooling methods on October 20, 2022

(3) emergent work activities following emergency diesel generator A trip on high jacket water temperature due to a loss of cooling flow on November 9, 2022

(4) emergent outage work activities for missing bolts from the main steam isolation valves on November 10, 2022

(5) component cooling water return from reactor coolant system isolation, EGHV0060, motor operated valve over trust emergent activities on November 30, 2022

71111.15 - Operability Determinations and Functionality Assessments

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

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

(1) turbine-and motor-driven auxiliary feedwater discharge flow control valves throttled when reactor power less than 10 percent operability determination on October 26, 2022

(2) train A load shedder and emergency load sequencers failure and repair operability determination on November 11, 2022

(3) steam generator D feedwater line flow acceleration corrosion inspection minimum wall operability determination on November 28, 2022

(4) steam generator atmospheric relief valve operability determination on November 29, 2022

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) permanent modification of the reactor vessel head to add canopy seal clamps additions on October 31, 2022

(2) permanent modification of the safety injection test line to add new isolation valves on November 4, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (9 Samples)

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

(1) emergency diesel generator B post-maintenance testing on October 31, 2022

(2) switchyard transformers 9 and 11 replacement post-maintenance testing on October 14, 2022

(3) switchyard transformers 8 and 10 replacement post-maintenance testing on November 9, 2022

(4) train A engineering safety feature transformer (XNB01) replacement post-maintenance testing on November 10, 2022

(5) train B ESW post-maintenance testing on October 28, 2022

(6) trains A and B residual heat removal post-maintenance testing on November 15, 2022

(7) reactor coolant pump D motor replacement post-maintenance testing on November 8, 2022

(8) feedwater valve isolation and main steam isolation valve post-maintenance testing on November 29, 2022

(9) main feedwater and bypass regulating valves on November 29, 2022

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated refueling outage 25 activities from October 6 through November 13, 2022.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) train A engineered safety features actuation system surveillance testing on November 13, 2022

(2) reactor coolant system pressure isolation valve BB8949A and D leakage test on November 18, 2022

(3) trains A and B 125 Vdc battery surveillance change frequency for surveillance requirement 3.8.4.3, 3.8.4.4, 3.8.4.5, and 3.8.4.7 on November 29, 2022

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

(1) train A ESW containment air coolers isolation valves EFHV0045 and EFHV0049 on December 1, 2022

FLEX Testing (IP Section 03.02) (1 Sample)

(1) spent fuel pool cooling and reactor core cooling FLEX pumps on November 29,

71124.01 - Radiological Hazard Assessment and Exposure Controls

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

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

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

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

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

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

(1) licensee surveys of potentially contaminated material leaving the radiologically controlled area

(2) workers exiting the containment building during a refueling outage

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

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

(1) code safety replacement in the pressurize cubicle on the 2068' elevation of the containment building using radiation work permit (RWP) 222000

(2) upper internals move from the reactor vessel to the lower cavity in preparation for fuel movement using RWP 226050

(3) radiography controls on the 2000' elevation of the containment building using RWP 223021

(4) fuel movement in the spent fuel pool during fuel reload activities using RWP 226060

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

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

(1) VHRA - containment building, 2000' in-core tunnel access

(2) HRA - auxiliary building, room 1302 demineralizer alley filter pits

(3) HRA - radwaste building, 2031' fuel pool cleanup demineralizer door (room 74061)

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

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

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

(1) control room emergency ventilation system A train (FGK01A)

(2) technical support services emergency ventilation (VT-F1)

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

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

(1) high efficiency particulate air filtration systems used during valve maintenance of the A loop check valve BB8948A and the letdown heat exchanger valve maintenance activities (BG8405A, BGTCV0381B, BG8107A, BG8408A, BGTCV0129)

(2) high efficiency particulate air filtration systems used to minimize airborne levels in the dry cavity with the temporary cover installed and underneath the reactor head while on the reactor head stand

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

(1) The inspectors evaluated the licensees use of respiratory protection devices.

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

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

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, 2021 through September 30, 2022

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

(1) October 1, 2021 through September 30, 2022

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

(1) April 1, 2021 through September 30, 2022

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) April 1, 2021 through September 30, 2022

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

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

(1) train A emergency diesel generator jacket water keep warm pump seal failure and extent of condition on November 30, 2022

(2) load shedder and emergency load sequencers card failures on December 30, 2022

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

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue associated with emergency preparedness drill performance declining trend on December 13, 2022.

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

(1) The inspectors evaluated an unauthorized individual who entered the protected area and licensees response on October 27, 2022.

(2) The inspectors evaluated loss of service water and emergency diesel generator A trip on high jacket water temperature and licensees response on November 1,

INSPECTION RESULTS

Failure to Perform Air flow Testing for Safety-Related Safety Injection Pump B Room Cooler (SGL09B)

Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.12 Systems NCV 05000482/2022004-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion XI, Test Control, for the licensees failure to establish testing requirements for the safety-related safety injection pump B room cooler to measure air flow, which resulted in the licensing failing to identify fan belt glazing and slippage resulted in degraded air flow and required belt replacement.

Description:

On June 7, 2022, the licensee identified 19 total blocked tubes (sediment) in the safety injection pump B room cooler (SGL09B) during the performance of work order (WO) 21-471133-003, which exceed the tube plugging limit of seven tubes. The licensees immediate corrective actions were to clean the blocked tubes and return room cooler SGL09B to service. The licensee initiated CR 10010541 and performed a past operability evaluation. This was documented in basic engineering disposition (BED), Blocked Tubes on SGL09B - CR 10015041, revision 0, and equipment performance evaluation.

The inspectors reviewed BED, Blocked Tubes on SGL09B - CR 10015041, revision 0, and equipment performance evaluation and identified the following:

The licensee did not trend room cooler SGL09B air flow to confirm that sufficient air flow was present to ensure its safety-related design function of maintaining safety injection pump room B temperatures were less than 122 oF for the degraded condition documented in CR 10015041. For room cooler SGL09B to maintain less than 122 oF room temperature, a minimum cooling capacity of 165,365 BTU/hour was required in accordance with calculation GL-M-007, Calculate Cooling Loads in SR Pump Rooms Post LOCA: 1107, 1108, 1109, 1110, 1111, 1112, 1113, 1114, 1401 and 1406, revision 0. This required a combination of room cooler air flow and ESW flow to the heat exchanger to achieve the required cooling capacity.

The licensee did not evaluate the past operability of containment spray pump B when the associated room cooler SGL13B was removed from service for planned maintenance on December 9, 2022. Specifically, procedure AP 26C-004, Operability Determination and Functionality Assessment, revision 46, provided guidance for the maximum ESW temperature for removing room cooler SGL13B from service without declaring train B containment spray pump inoperable in accordance with calculation XX-M-080, Wolf Creek Generating Station Pump Room Heat-up Analysis, revision 1, which assumed room cooler SGL09B air flow was 10,092 cubic feet per minute (cfm).

In response the inspectors questions, the following was identified:

Room cooler SGL09B air flow was last measured December 20, 2012, in accordance with WO 12-362212-003 following fan belt replacement. The measured air flow was 10,116 cfm during the post-maintenance testing, but the licensee failed to apply the instrument uncertainty of +/- 3.00 percent. When applying the instrument uncertainty actual air flow was determined to be 9,812 cfm which was less than the design air flow requirement of 10,092 cfm (10,395 cfm with instrument uncertainty). The licensee initiated CRs 10016320 and 10016321, and measured room cooler SGL09B air flow on July 28, 2022, in accordance with WO 22-480641-000 with a measured air flow of 9,117 cfm and commenced troubleshooting of low air flow for room cooler SGL09B in accordance with WO 22-480641-001. The troubleshooting identified that fan belts where slipping and glazed meeting the requirement for replacement in accordance with procedure MPE RC-001, Room Cooler Maintenance, revision 13. Specifically, procedure MPE RC-001, step 7.7.2.2.a, specified replacement of belts if worn, cracked, frayed, or cords are exposed or there is glazing on the sidewalls. The licensee replaced fan belts and performed post-maintenance testing satisfactory with a measured air flow of 11,261 cfm. The licensee reperformed the past operability and documented in BED, Blocked Tubes on SGL09B - CR 10015041, revision 1, and determined room cooler SGL09B was able to perform its safety function of maintained room less than 122 oF and containment spray pump B operable with room cooler SGL13B unavailable for maintenance. The licensee initiated CRs 10016406 and 10017443 to capture this issue in the corrective action program.

After July 2016, the licensee discontinued safety-related room cooler heat transfer verification and performance trending and relied on safety-related room cooler maintenance and inspections performed in accordance with MPE RC-001 and monitoring of ESW flow and differential pressure. However, the licensee failed to recognize the need to establish procedures to monitor air flow and have an acceptance criterion for safety-related room coolers to ensure sufficient air flow was available to meet the safety function of maintaining room temperature less than 122 oF.

Room cooler SGL09B fan coil unit inspections were last performed under WO 20-463868-000 (December 3, 2020) and WO 21-471121-000 (December 6, 2021)and the licensee failed to identify the degraded condition of the fan belts, which required replacement in accordance with procedure MPE RC-001, step 7.7.2.2.a, causing the degraded air flow.

The inspectors concluded the licensee failed to recognize the need to establish procedures to measure safety-related room cooler air flow at a required frequency and acceptance criterion to identify a degraded condition associated with the safety-related room coolers after discontinuing heat transfer verification and performance trending in July 2016.

Corrective Actions: The licensees corrective actions included replacing room cooler SGL09B degraded fan belts, performing extent of condition, evaluating safety-related room cooler air flow testing requirements, and establishing a 5-year preventative maintenance for fan belt replacement.

Corrective Action References: CRs 10016406, 10016320, 10016321, and 10017443

Performance Assessment:

Performance Deficiency: The licensees failure to establish testing requirements to measure air flow for safety-related room coolers to demonstrate that they will perform satisfactorily and to detect degraded performance 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 licensee failing to establish testing requirements for SGL09B to measure air flow resulted in the licensing failing to identify the degraded air flow caused by fan belt glazing and slippage.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be of very low safety significance (Green) because it,

(1) was not a deficiency affecting the design or qualification of a mitigating system,

(2) does not represent a loss of the probability risk analysis (PRA) function of a single train technical specification system for greater than its allowed outage time,

(3) does not represent a loss of PRA function of one train of a multi-train technical specification system for greater than its allowed outage time,

(4) does not represent a loss of the 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) does not represent a loss of PRA system and/or function as defined by the plant risk information e-book or the licensees PRA 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) does not result in the loss of a high safety-significant, nontechnical specification train for greater than 3 days.

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance. Specifically, in July 2016 the licensee discontinued the representative safety-related room cooler heat transfer testing program and relied on periodic inspection and maintenance to determine if they can meet their design function of maintaining room temperatures less than 122 oF.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XI, Test Control, requires, in part, that a test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.

Contrary to the above, from July 2016 to December 2022, the licensee failed to establish a test program to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. Specifically, the licensee failed to establish testing requirements for the safety-related safety injection pump B room cooler SGL09B to measure air flow resulted in the licensing failing to identify fan belt glazing and slippage resulting in degraded air flow and required belt replacement.

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

Observation: Semi-Annual Trend Review 71152S The inspectors reviewed the licensees corrective action program, performance indicators, system health reports, and other documentation available to help identify performance trends that might indicate the existence of a more significant safety issue. The inspectors verified that the licensee was taking corrective actions to address the identified adverse trends. The inspectors did not review any cross-cutting themes because none existed at the site.

To verify the licensee was taking corrective actions to address identified adverse trends that might indicate the existence of a more significant safety issue, the inspectors noted a trend in emergency response organization (ERO) vacancies. Specifically, the inspectors noted 18 CRs for ERO vacancies for November 2022 and 35 CRs for ERO vacancies for calendar year 2022. These recent ERO vacancies are due to retirement as well as previous large-scale turnover that occurred at the station. This has the potential to cause significant knowledge and performance gaps within the ERO. In response to the inspectors observation, the licensee-initiated CR 10021065 to perform a trend analysis to determine if any areas within ERO need additional focus and to assess the aggregate impact of the loss of experience.

EXIT MEETINGS AND DEBRIEFS

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

On November 7, 2022, the inspectors presented the occupational radiation safety inspection results to Jaime McCoy, Site Vice President, and other members of the licensee staff.

On November 22, 2022, the inspectors presented the inservice inspection results to Mike Boyce, Engineering Vice President, and other members of the licensee staff.

On January 10, 2023, the inspectors presented the integrated inspection results to Jaime McCoy, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures AI 14-006 Severe Weather 19

71111.01 Procedures AP 21C-001 Wolf Creek Substation 22

71111.01 Procedures AP 22B-001 Outage Risk Management 22

71111.01 Procedures OFN SG-003 Natural Events 39

71111.04 Corrective Action Condition Reports 10019036, 10019635, 10019638

Documents

71111.04 Drawings DK-7496 One Line Diagram 78

71111.04 Procedures OFN AF-025 Unit Limitations 59

71111.04 Procedures SYS NB-200 Transferring XNB01 Supply Between #8 Transformer and #9 22

Transformer Using NE01

71111.04 Procedures SYS SL-204 Transferring Bus 13.8 kV Supplies Between XFMR #8/10 0

and #9/11

71111.05 Corrective Action Condition Report 10018713, 10013103, 10017895

Documents

71111.05 Corrective Action Condition Report 10018526

Documents

Resulting from

Inspection

71111.05 Miscellaneous 10013103 - Root 10013103 - Root Cause Analysis for Missed Fire Watch 1

Cause Analysis Checks

71111.05 Miscellaneous E-1F9910 Post Fire Safe Shutdown Area Analysis 17

71111.05 Procedures AP 10-106 Fire Preplans 22

71111.08P Calculations W-SMT-95-100 Westinghouse Analysis for SI Hot Leg Loop 2 & 3 Snubber 1

Analysis - Reactor Building

71111.08P Calibration WC014912 Calibration of Various Force Indicating Devices: 02/23/2022

Records Dynamometer (Dillon) AP D901837

71111.08P Calibration WC019104 Calibration of Various Force Indicating Devices: 02/23/2022

Records Dynamometer (Dillon) D D-22156

71111.08P Calibration WC019105 Calibration of Various Force Indicating Devices: 05/24/2022

Records Dynamometer (Dillon) D D-22155

71111.08P Corrective Action CR 10018557 Boric Acid Residue RBB01 top head 10/16/2022

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Corrective Action CR 10018704 EMV0110 Dry White Boron Leakage from Packing 10/18/2022

Documents

71111.08P Corrective Action CR 10018704 EMV0110 Dry White Boron Leakage from Packing 10/18/2022

Documents

71111.08P Corrective Action CR 10018949 EMV0110 Dried White Boron Accumulation 10/20/2022

Documents

Resulting from

Inspection

71111.08P Engineering SAP-PP000-TR-Assessment of the Wolf Creek Accumulator Loop 1 and 0

Evaluations PX-000001 Safety Injection Loop 3 Piping Lines due to the Inclusion of

Cold Spring Effects (Westinghouse Electric Company LLC)

71111.08P Miscellaneous WCRE-30 Inservice Inspection Program Plan - Wolf Creek Generating 5

Station - Interval 4

71111.08P NDE Reports 180-9326103-000 Framatome NDE Services Final Report: Wolf Creek Unit 1 - 04/18/2021

RF24 RVCH Penetration Examination Report

71111.08P NDE Reports 21-473988-000 RVH Visual Inspection Report 11/12/2022

71111.08P Procedures AI 16F-001 Evaluation of Boric Acid Leakage 11A

71111.08P Procedures AI 16F-002 Boric Acid Leakage Management 12

71111.08P Procedures AP 15C-004 Preparation, Review and Approval of Procedures, 55A

Instructions and Forms

71111.08P Procedures AP 16F-001 Boric Acid Corrosion Control Program 10A

71111.08P Procedures LMT-08-MT-01 Magnetic Particle Examination 0

71111.08P Procedures LMT-08-UT-004 Ultrasonic Examination of Vessel Welds and Adjacent Base 1

Metal >2" in Thickness

71111.08P Procedures STS PE-040E RPV Head Visual Inspection 9

71111.08P Work Orders WO 18-445398-SI Accum to Loop 1 Check Valve (BB8948A). Westinghouse 10/21/2022

Calculation allows pipe to be cold sprung

71111.08P Work Orders WO 18-445399-Safety Injection RHR to Loop 3 Check Valve (BB8949C). 10/22/2022

21 Westinghouse Calculation allows pipe to be cold sprung.

71111.08P Work Orders WO 21-474032-RF25 ISI Examination of EBB01A-16-W (UT and MT of 11/02/2022

2 S/G 1 Steam line weld)

71111.08P Work Orders WO 22-482488-Reactor Vessel Head - Potential indication of seal weld 10/21/2022

000 leakage on Penetration-19 during the performance of STS

PE-040E. Performance of a dye penetrant test is needed to

Inspection Type Designation Description or Title Revision or

Procedure Date

confirm if this indication is an actual seal weld leak.

71111.11Q Procedures EMG E-0 Reactor Trip or Safety Injection 45

71111.11Q Procedures GEN 00-004 Power Operation 101

71111.12 Calculations XX-M-080 Wolf Creek Generating Station Pump Room Heat-up 1

Analysis

71111.12 Calculations DEB Blocked Tubes on SGL09B - CR 10015041 1

71111.12 Calculations EG-M-055 Overload Evaluation for Anchor-Darling Double-Disc Wedge 0

Gate Valve

71111.12 Calculations GL-M-007 Calculate Cooling Load in SR Pump Rooms Post LOCA: 0

1107, 1108, 1109, 1110, 1111, 1112, 1113, 1114, 1401, and

1406

71111.12 Calculations XX-M-080 Wolf Creek Generating Station Pump Room Heat-Up 1

Analysis

71111.12 Corrective Action Condition Reports 10001155, 10001305, 10001975, 10007983, 10010737,

Documents 10011933, 10012377, 10019061, 10016320, 10016321,

10016406, 10016449, 10017201, 10017205, 10017212,

10017625, 10020153

71111.12 Corrective Action Condition Reports 10017443, 10017590, 10017591

Documents

Resulting from

Inspection

71111.12 Engineering DCP 20390 Containment Purge Isolation Zone 0

Changes

71111.12 Miscellaneous 2018-011 USAR Change Request 07/10/2018

71111.12 Miscellaneous 2020-012 USAR Change Request 09/16/2020

71111.12 Miscellaneous 2021-010 USAR Change Request 09/21/2021

71111.12 Miscellaneous ET 16-0017 Updated Response to Generic Letter 89-13 07/26/2016

71111.12 Miscellaneous WCRE-35 Boundary Matrix 9

71111.12 Procedures AP 16E-002 Post Maintenance Testing Development 21A

71111.12 Procedures AP 23L-002 Heat Exchanger Program 5

71111.12 Procedures AP 26C-004 Operability Determination and Functionality Assessment 46

71111.12 Procedures EDI 23M-060 Engineering Desktop Instruction Performing Maintenance 0

Rule Periodic Assessments

71111.12 Procedures MPE RC-001 Room Cooler Maintenance 13

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Procedures MPM XX-002 Watertight Doors Preventive Maintenance Activity 7B

71111.12 Procedures OFN EF-033 Loss of Essential Service Water 24

71111.12 Procedures STN PE-036 Safety Related Room Cooler Heat Transfer Verification and 16, 17

Performance Trending

71111.12 Procedures STN PE-037B ESW Train B Heat Exchanger Flow and DP Trending 25

71111.12 Procedures STS PE-004 Aux Building and Control Room Pressure Test 20

71111.12 Procedures STS PE-007 Periodic Verification of Motor Operated Valves 5A

71111.12 Procedures SYS PE-175 LLRT Valve Lineup for Penetration 75 19

71111.12 Work Orders WO 12-362212-003, 20-463868-000, 21-469071-000,

21-469227-000, 21-471121-000, 21-472265-000,

21-473840-001, 21-475179-003, 21-475179-004,

2-478271-000, 22-480641-001, 22-482475-000,

2-482475-001

71111.13 Corrective Action Condition Reports 10018514, 10018670, 10018671, 10018701, 10018757,

Documents 10018763, 10018910, 10019558, 10019604, 10019607,

10019608, 10019610, 10019613, 10019719, 10019741,

10019773

71111.13 Corrective Action Condition Reports 10018198, 10018731, 10018890, 10020846

Documents

Resulting from

Inspection

71111.13 Drawings KD-7496 One Line Diagram 76

71111.13 Drawings WIP-KD-2796-One Line Diagram 0

073-B-1

71111.13 Miscellaneous APF 22B-001-09 Shutdown Risk Assessment No Mode - Defueled 14

71111.13 Miscellaneous APF 22B-001-10 Shutdown Safety Function Status and Assessment 13

Summary

71111.13 Procedures AP 22B-001 Outage Risk Management 21

71111.13 Procedures OFN EC-046 Fuel Pool Cooling and Cleanup Malfunctions 9

71111.13 Procedures STS KJ-011A EDG NE01 24 Hour Run 39

71111.13 Procedures SYS EC-202 Staging Alternate Spent Fuel Pool Cooling 4

71111.13 Work Orders WO 21-473967-000, 22-482773-000, 22-482773-001,

2-482773-002, 22-482773-003, 22-482773-004,

2-482793-000,

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Calculations 59606-M-001 Design Minimum Wall Thickness Values for Piping Bends 1

and Elbows in Main Feedwater Piping Located in

Containment

71111.15 Calculations AN-99-019 Radiological Consequences of the Main Steam Line Break 0

Outside Containment

71111.15 Corrective Action Condition Report 96-0794, 2006-000188, 123051, 123932, 10018783,

Documents 10019400, 10019761, 10019779, 10019819, 10019926,

10020042, 10020303

71111.15 Corrective Action Condition Report 10019205, 10020411

Documents

Resulting from

Inspection

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

System

71111.15 Engineering DECP 20617 Alternate IP Transducer for SG Atmospheric Relief Valves 0

Changes

71111.15 Miscellaneous USAR Change Request 98-138 11/20/1998

71111.15 Miscellaneous DRR 06-1350 Document Revision Request 0

71111.15 Miscellaneous EQSD-I Equipment Qualification Design Basis Document 16

71111.15 Miscellaneous M-10AL Auxiliary Feedwater System 1

71111.15 Miscellaneous PQE-J-601B-P02 Atmospheric Relief Valves GT25 I/P Transducer 0

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

71111.15 Procedures AI 21-016 Operator Time Critical Actions Validation 21A

71111.15 Procedures EMG E-0 Reactor Trip or Safety Injection 45

71111.15 Procedures EMG E-2 Faulted Steam Generator Isolation 24A

71111.15 Procedures EMG ES-03 SI Termination 29

71111.15 Procedures STS AL-201C Turbine Driven Auxiliary Feedwater System Inservice Valve 13

Test

71111.15 Procedures SYS AL-120 Motor Driven or Turbine Driven AFW Pump Operations 56

71111.15 Work Orders WO 21-472871-002, 21-474872-001, 21-474872-003,

2-482825-000

71111.18 Calculations 0720517.01-C-Wolf Creek Generating Station Simplified Head Assembly 1

001 (SHA) Drop Analysis

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.18 Corrective Action Condition Reports 2003-3473, 10019193, 100005074

Documents

71111.18 Corrective Action Condition Report 10019243

Documents

Resulting from

Inspection

71111.18 Drawings M-703-00054 Closure Head General Assembly W16

71111.18 Engineering CCP 012962 Canopy Seal Clamp Assembly in Capped Latch Location 0

Changes

71111.18 Engineering CCP 07910 Canopy Seal Clamp Assembly for Spare Penetrations 0

Changes

71111.18 Engineering CCP 10132 Canopy Seal Clamp Installation on Penetration 10 0

Changes

71111.18 Engineering DCP 05017 Canopy Seal Clamp Assemblies 0

Changes

71111.18 Engineering DECP 020328 Spare CET Canopy Seal Clamp Documentation Update 0

Changes

71111.18 Miscellaneous DRR 22-0019 Document Revision Request FHP 02-007A 0

71111.18 Miscellaneous WCNOC-4 Report on Control of Heavy Loads 21

71111.18 Procedures FHP 02-0007D Load Cell Set Up and Use 4

71111.18 Procedures FHP 02-007A Reactor Vessel Closure Head Removal 16

71111.18 Procedures FHP 02-007B Reactor Vessel Closure Head Installation 17

71111.18 Procedures MCM BB-007 Installation and Removal Canopy Seal Clamp Assemblies 8

(CSCA)

71111.18 Work Orders WO 18-442877-008, 18-442486-000, 18-442486-001,

20-458773-000, 21-458773-001, 21-471334-000

71111.19 Corrective Action Condition Reports 10017597, 10018224, 10018279, 10018346, 10018353,

Documents 10018378, 10018383, 10018398, 10018400, 10018437,

10018452, 10018460, 10018491, 10018500, 10018505,

10018510, 10018517, 10018546, 10018574, 10018606,

10018610, 10018612, 10018613, 10018626, 10018657,

10018677, 10018690, 10018771, 10018777, 10018834,

10018839, 10018881, 10018908, 10018972, 10018973,

10018982, 10018986, 10018992, 10019147, 10019150,

Inspection Type Designation Description or Title Revision or

Procedure Date

10019223, 10019290, 10019291, 10019292, 10019299,

10019311, 10019314, 10019324, 10019335, 10019410,

10019411, 10019415, 10019416, 10019434, 10019441,

10019470, 10019558, 10019597, 10019729, 10019745,

10019821, 10019826, 10019831, 10019837, 10019843,

10019846, 10019941, 10019967, 10019974, 10020179,

10020189, 10020213, 10020221, 10020263, 10020265,

10020484, 10020471, 10020501, 10020503

71111.19 Corrective Action Condition Report 10019548

Documents

Resulting from

Inspection

71111.19 Drawings E-13AE06 Schematic Diagram Main Feedwater Control Valves 2

71111.19 Drawings M-018-00586 P9826 Crankcase Vac Ejector Application W04

71111.19 Drawings M-12AE01 Piping and Instrumentation Diagram Feedwater System 50

71111.19 Drawings M-12EJ01 Piping and Instrumentation Diagram Residual Heat Removal 57

System

71111.19 Drawings M-12EP01 Piping and Instrumentation Diagram Accumulator Safety 17

Injection

71111.19 Engineering CP 20662 Replacement Cap Screw for AEFV0041 0

Changes

71111.19 Engineering DCP 020292 Substation Transformer No. 8, 9, 10, & 11 and Breaker 0

Changes Replacement R25

71111.19 Engineering DECP Main Feedwater Reg Valve Body to Bonnet Stud Repair and 0

Changes Chamfering of Existing Studs

71111.19 Miscellaneous BED ESC Item 23 - MSIV ABHV0014 Discs Stelite Hardfacing 0

Cracks

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

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

71111.19 Procedures MEC-039 Emergency Diesel Engine Injection Nozzle Testing 1

71111.19 Procedures MPM KJ-006 Emergency Diesel Rocker Lube Oil Strainer Cleaning 0

71111.19 Procedures STS AE-205 Feedwater System Inservice Valve Test 28

71111.19 Procedures STS AE-207 Feed Reg Valve Inservice Valve Test 3

71111.19 Procedures STS CV-210A ECCS SI Comprehensive Pump and Inservice Check Valve 28

Inspection Type Designation Description or Title Revision or

Procedure Date

Testing

71111.19 Procedures STS IC-611A Slave Relay Test K611 K612 K613 Train A Feedwater 15

Isolation

71111.19 Procedures STS KJ-001A Integrated D/G and Safeguards Actuation Test - Train A 71

71111.19 Procedures SYS NB-202 Transferring NB02 Power Sources 60

71111.19 Work Orders WO 15-406288-000, 17-434046-072, 19-456339-000,

21-470674-007, 21-470674-023, 21-471360-017,

21-472467-054, 21-473908-000, 21-474084-000,

21-474731-000, 21-475054-006, 21-475054-005,

2-479954-000, 22-479956-000, 22-482373-000,

2-482422-002, 22-482603-000, 22-482802-009,

2-482898-000, 22-483098-000, 22-483101-000

71111.20 Corrective Action Condition Reports 10018507, 10018511, 10018513, 10018524, 10018580,

Documents 10018584, 10018637, 10018676, 10018695, 10018721,

10019038, 10019184, 10019693, 10019784, 10019791,

10019793, 10020031, 10020032, 10020346, 10020052

71111.20 Corrective Action Condition Report 10018622, 10019805, 10019923, 10020191, 10020192,

Documents 10020292, 10020293, 10020294, 10020295, 10020297

Resulting from

Inspection

71111.20 Procedures GEN 00-005 Minimum Load to Hot Standby 95

71111.20 Procedures GEN 00-006 Hot Standby to Cold Shutdown 106

71111.20 Procedures GEN 00-008 RCS Level Less Than Reactor Vessel Flange Operations 36

71111.20 Procedures GEN 00-009 Refueling 47

71111.20 Procedures OFN BB-031 Shutdown LOCA 36A

71111.20 Procedures OFN EG-004 CCW System Malfunction 19

71111.20 Procedures OFN EJ-015 Loss of RHR Cooling 33

71111.20 Procedures OFN EJ-040 CL Recirc During Mode 3, with Accumulators Isolated, 8

Mode 4, 5, or 6

71111.20 Procedures STS BB-011 Reactor Coolant System and Pressurizer Heatup/Cooldown 34

Surveillance

71111.20 Procedures STS BG-001 Boron Injection Flow Path Verification 25

71111.20 Procedures STS CR-002 Shift Log for Modes 4, 5, and 6 92

71111.20 Procedures SYS EJ-120 Startup of a Residual Heat Removal Train 73

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Calculations FD-13-007 AFW FLEX Hydraulic Evaluation 0

71111.22 Corrective Action Condition Reports 10003430, 10003431, 10018003, 10018558, 10018559,

Documents 10018639, 10018692, 10018733, 10018790, 10018795,

10018880, 10018897, 10018946, 10018966, 10018988,

10019329, 10019330, 10019348, 10019386, 10019413,

10019448, 10019555, 10019688, 10019690, 10019696,

10019753, 10019829, 10019836, 10020028, 10020184,

10020190, 10020647, 10020784

71111.22 Corrective Action Condition Report 10019820

Documents

Resulting from

Inspection

71111.22 Drawings M-12EF02 Piping Instrumentation Diagram Essential Service Water 43

System

71111.22 Miscellaneous MS-01 Piping Class Summary 87

71111.22 Miscellaneous STRIDE 22-00 Wolf Creek (18 months) NK (125 VDC Class 1E) Batteries 0

Surveillance

71111.22 Miscellaneous WCNOC-182 Operations and Maintenance Manual Spent Fuel Pool W02

Makeup Pump

71111.22 Miscellaneous WCNOC-186 Operations and Maintenance Manual Core Cooling Pump W01

71111.22 Miscellaneous WCRE-34 WCNOC Fourth 10-Year Interval Inservice Testing Program 12

71111.22 Miscellaneous WCRE-38 Surveillance Frequency Control Program Surveillance Test 0

Interval List

71111.22 Procedures AP 05C-005 PRA Methodology for Evaluating Changes to Surveillance 0

Test Intervals

71111.22 Procedures AP 21A-002 Diverse and Flexible Coping Mitigation (FLEX) Program 3A

71111.22 Procedures AP 29-009 Surveillance Test Risk Informed Documented Evaluation 0

(STRIDE) Process

71111.22 Procedures AP 29-011 Surveillance Frequency Control Program 0

71111.22 Procedures AP 29E-001 Program Plan for Containment Leakage Measurements 17

71111.22 Procedures STS MT-021 Service Test for 125 VDC Class 1E Batteries 18

71111.22 Procedures STS MT-080 125 Volt DC Battery Inspection 1

71111.22 Procedures STS PE-018 Containment Integrated Leakage Rate Test 9

71111.22 Procedures STS PE-171 LLRT Valve Lineup for Penetrations 71 and 73 9

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Procedures STS PE-261 LLRT Valve Lineup for Penetration 161 7

71111.22 Procedures SYS GP-515 CILRT-EF System 2

71111.22 Work Orders WO 21-476771-000, 22-476912-000, 22-476912-001

71124.01 Corrective Action Condition Reports 10002460, 10003015, 10003660, 10003789, 10003935,

Documents 10004384, 10004685, 10004833, 10012104, 10015213,

10016703, 10017231, 10017940, 10018158, 10018831,

10019497, 10019533, 10020039

71124.01 Miscellaneous 2021 RWP Budget vs Actuals (Outage/Non-Outage): Outage 09/28/2022

March 25, 2021 through May 15, 2021

71124.01 Miscellaneous 2022 ALARA and RWP Quick Look Report 09/12/2022

71124.01 Miscellaneous 330342 Access Control Shift Log 10/18/2022

71124.01 Procedures AP 25A-001 Radiation Protection Manual 20

71124.01 Procedures AP 25A-200 Access to Locked High or Very High Radiation Areas 29

71124.01 Procedures AP 25A-401 ALARA Program 28

71124.01 Procedures AP 25B-100 Radiation Worker Guidelines 55

71124.01 Procedures RPP 02-105 RWP (Radiation Work Permits) 52

71124.01 Procedures RPP 02-205 Radiological Survey Frequency Requirements 15

71124.01 Procedures RPP 02-215 Posting of Radiological Controlled Areas 34B

71124.01 Procedures RPP 02-405 RCA Access Control 21

71124.01 Procedures RPP 02-515 Release of Material from the RCA 36

71124.01 Procedures RPP 07-212 Requirements of Radioactive Materials Stored Outdoors 0

71124.01 Radiation 22-0071 Airborne Radioactivity Record: Auxiliary Building 2000' 05/11/2022

Surveys

71124.01 Radiation 22-0072 Airborne Radioactivity Record: Auxiliary Building 2000' 05/11/2022

Surveys

71124.01 Radiation 22-0170 Airborne Radioactivity Record: Fuel Building 2047' and 08/22/2022

Surveys above

71124.01 Radiation 22-0174 Airborne Radioactivity Record: Fuel Building 2047' and 08/22/2022

Surveys above

71124.01 Radiation M-20220719-8 Demin alley 07/19/2022

Surveys

71124.01 Radiation M-20221018-42 2000' CTMT "D" Loop, BB8949D Dose rate alarm follow-up 10/18/2022

Surveys

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.01 Radiation M-20221030-3 CTMT B/C Secondary follow-up for dose rate alarm 10/30/2022

Surveys

71124.01 Radiation M-20221101-2 Letdown Cubicle 11/01/2022

Surveys

71124.01 Radiation RT Work Order: Radiography posting and guarding locations in containment 11/01/2022

Surveys 20-462202-007

71124.01 Radiation Work 220020 Waste processing activities, cartridge filter change out, and 0

Permits (RWPs) resin transfer

71124.01 Radiation Work 221102 In-core Tunnel Inspections, Maintenance and 0

Permits (RWPs) Decontamination

71124.01 Radiation Work 222000 Mechanical Maintenance activities 0

Permits (RWPs)

71124.01 Radiation Work 222601 Routine Access 0

Permits (RWPs)

71124.01 Radiation Work 223021 Radiography activities 0

Permits (RWPs)

71124.01 Radiation Work 224461 Motor Operated Valves Team activities. 0

Permits (RWPs)

71124.01 Radiation Work 226020 Reactor Vessel Head Lift Preparation and Post Head Set 0

Permits (RWPs) Work Activities

71124.01 Radiation Work 226050 Reactor Vessel Upper Internals removal, transfer, and 0

Permits (RWPs) replacement

71124.01 Radiation Work 226060 Fuel Movement and Related Support Activities 0

Permits (RWPs)

71124.01 Self-Assessments 22-01-RP/C Quality Assurance Standard Audit Checklist: 01/20/2022

Radiological Protection & Process Control

71124.03 Corrective Action Condition Reports 10006532, 10009497, 10009726, 10015620, 10016405

Documents

71124.03 Miscellaneous Site Air Sample Logs: April 1, 2021 - September 13, 2022

71124.03 Miscellaneous 2020 ANI Nuclear Liability Insurance Inspection Response 03/31/2021

71124.03 Miscellaneous Trace Analytics, Certificates of Analysis - January 19, 2021

through October 22, 2022

71124.03 Miscellaneous AIF 10-001-02 Monthly SCBA Inspections - May 2021 through September

22

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.03 Miscellaneous K15-002 22-01-Quality Assurance Standard Audit Checklist - Radiological 01/20/2022

RP/PC Protection & Process Control: January 10 - January 20, 2022

71124.03 Miscellaneous STS PE-002-Charcoal Adsorbent Sampling for Nuclear Safety Related 07/06/2022

FGG02A Units - FGG02A

71124.03 Miscellaneous STS PE-002-Charcoal Adsorbent Sampling for Nuclear Safety Related 08/23/2022

FGG02B Units - FGG02B

71124.03 Miscellaneous STS PE-005-HEPA Filter In-Place Leak Test Safety Related Units - 08/15/2022

FGG02B FGG02B

71124.03 Miscellaneous STS PE-006-Charcoal Adsorber In-Place Leak Test Safety Related Units - 08/15/2022

FGG02B FGG02B

71124.03 Miscellaneous STS PE-006-Charcoal Adsorber In-Place Leak Test Safety Related Units - 03/03/2022

FGK02B FGK02B

71124.03 Miscellaneous STS-PE-005-HEPA Filter In-Place Leak Test Safety Related Units - 02/21/2022

FGK01B FGK01B

71124.03 Procedures AI 10-004 Air Fill Station Operation 4A

71124.03 Procedures AI 14-009 Industrial Respiratory Protection Program 7

71124.03 Procedures AP 25B-100 Radiation Worker Guidelines 55

71124.03 Procedures MCE CF-001 Filtration Units Bulk Spent Charcoal Changeout 1A

71124.03 Procedures MCE CF-002 Filtration Unit Spent Charcoal Tray Replacement 3

71124.03 Procedures RPP 05-607 Operation of the Portacount 14A

71124.03 Procedures STS PE-002 Charcoal Adsorbent Sampling for Nuclear Safety Related 15

Units

71124.03 Procedures STS PE-005 HEPA Filter In-Place Leak Test Safety Related Units 13

71124.03 Procedures STS PE-006 Charcoal Adsorber In-Place Leak Test Safety Related Units 17

71124.03 Radiation Work 220061 Fuel Building Transfer Canal Entry for Repair/Inspection and 1

Permits (RWPs) Decon of Fuel Building Transfer System.

71151 Miscellaneous RA 22-0038 2021 Annual Radioactive Effluent Release Report - Report 04/25/2022

71151 Miscellaneous STN CH-024 Wolf Creek Generating Station ODCM Surveillance Reports:

22 January through September

71151 Procedures STN CH-024 Quarterly/Yearly Dose Projections 4

71152A Corrective Action Condition Reports 20499, 96405, 99718, 10011538, 10019657, 10020251,

Documents 10020290, 10020304

71152A Procedures AP 02B-002 Closed Cooling Water Chemistry Control 7

Inspection Type Designation Description or Title Revision or

Procedure Date

71152A Work Orders WO 19-456413-000

71152S Corrective Action Condition Reports 10013158, 10013210, 10013236, 10013254, 10014124,

Documents 10014211, 10014212, 10014598, 10014599, 10014600,

10014601, 10014602, 10014603, 10018450, 10020738,

10020739, 10020740, 10020741, 10020742, 10020743,

10020770, 10020771

71152S Corrective Action Condition Report 10021065

Documents

Resulting from

Inspection

71152S Miscellaneous 22-05-EP Quality Assurance Audit Report (Emergency Preparedness) 06/06/2022

71152S Miscellaneous SA-2021-0171 EP Program and PI Self-Assessment 03/24/2022

71153 Corrective Action Condition Reports 10019281, 10019287, 10019604, 10019607, 10019608,

Documents 10019610, 10019613

71153 Procedures OFN EF-033 Loss of Essential Service Water 24

27