IR 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:
Report Number:
Enterprise Identifier:
I-2022-004-0002
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
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 Aspect Report Section Mitigating Systems Green NCV 05000482/2022004-01 Open/Closed None (NPP)71111.12 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.
REACTOR SAFETY
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,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee 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 Aspect Report Section Mitigating Systems Green NCV 05000482/2022004-01 Open/Closed None (NPP)71111.12 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AI 14-006
Severe Weather
Procedures
Wolf Creek Substation
Procedures
Outage Risk Management
Procedures
OFN SG-003
Natural Events
Corrective Action
Documents
Condition Reports
10019036, 10019635, 10019638
Drawings
DK-7496
One Line Diagram
Procedures
OFN AF-025
Unit Limitations
Procedures
SYS NB-200
Transferring XNB01 Supply Between #8 Transformer and #9
Transformer Using NE01
Procedures
SYS SL-204
Transferring Bus 13.8 kV Supplies Between XFMR #8/10
and #9/11
Corrective Action
Documents
Condition Report
10018713, 10013103, 10017895
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10018526
Miscellaneous
10013103 - Root
Cause Analysis
10013103 - Root Cause Analysis for Missed Fire Watch
Checks
Miscellaneous
E-1F9910
Post Fire Safe Shutdown Area Analysis
Procedures
AP 10-106
Fire Preplans
Calculations
W-SMT-95-100
Westinghouse Analysis for SI Hot Leg Loop 2 & 3 Snubber
Analysis - Reactor Building
Calibration
Records
WC014912
Calibration of Various Force Indicating Devices:
Dynamometer (Dillon) AP D901837
2/23/2022
Calibration
Records
WC019104
Calibration of Various Force Indicating Devices:
Dynamometer (Dillon) D D-22156
2/23/2022
Calibration
Records
WC019105
Calibration of Various Force Indicating Devices:
Dynamometer (Dillon) D D-22155
05/24/2022
Corrective Action
Documents
CR 10018557
Boric Acid Residue RBB01 top head
10/16/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 10018704
EMV0110 Dry White Boron Leakage from Packing
10/18/2022
Corrective Action
Documents
CR 10018704
EMV0110 Dry White Boron Leakage from Packing
10/18/2022
Corrective Action
Documents
Resulting from
Inspection
CR 10018949
EMV0110 Dried White Boron Accumulation
10/20/2022
Engineering
Evaluations
SAP-PP000-TR-
PX-000001
Assessment of the Wolf Creek Accumulator Loop 1 and
Safety Injection Loop 3 Piping Lines due to the Inclusion of
Cold Spring Effects (Westinghouse Electric Company LLC)
Miscellaneous
WCRE-30
Inservice Inspection Program Plan - Wolf Creek Generating
Station - Interval 4
NDE Reports
180-9326103-000
Framatome NDE Services Final Report: Wolf Creek Unit 1 -
RF24 RVCH Penetration Examination Report
04/18/2021
NDE Reports
21-473988-000
RVH Visual Inspection Report
11/12/2022
Procedures
AI 16F-001
Evaluation of Boric Acid Leakage
11A
Procedures
AI 16F-002
Boric Acid Leakage Management
Procedures
Preparation, Review and Approval of Procedures,
Instructions and Forms
55A
Procedures
Boric Acid Corrosion Control Program
10A
Procedures
LMT-08-MT-01
Magnetic Particle Examination
Procedures
LMT-08-UT-004
Ultrasonic Examination of Vessel Welds and Adjacent Base
Metal >2" in Thickness
Procedures
STS PE-040E
RPV Head Visual Inspection
Work Orders
WO 18-445398-
SI Accum to Loop 1 Check Valve (BB8948A). Westinghouse
Calculation allows pipe to be cold sprung
10/21/2022
Work Orders
WO 18-445399-
21
Safety Injection RHR to Loop 3 Check Valve (BB8949C).
Westinghouse Calculation allows pipe to be cold sprung.
10/22/2022
Work Orders
WO 21-474032-
2
RF25 ISI Examination of EBB01A-16-W (UT and MT of
S/G 1 Steam line weld)
11/02/2022
Work Orders
WO 22-482488-
000
Reactor Vessel Head - Potential indication of seal weld
leakage on Penetration-19 during the performance of STS
PE-040E. Performance of a dye penetrant test is needed to
10/21/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
confirm if this indication is an actual seal weld leak.
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
GEN 00-004
Power Operation
101
Calculations
XX-M-080
Wolf Creek Generating Station Pump Room Heat-up
Analysis
Calculations
DEB
Blocked Tubes on SGL09B - CR 10015041
Calculations
EG-M-055
Overload Evaluation for Anchor-Darling Double-Disc Wedge
Gate Valve
Calculations
GL-M-007
Calculate Cooling Load in SR Pump Rooms Post LOCA:
1107, 1108, 1109, 1110, 1111, 1112, 1113, 1114, 1401, and
1406
Calculations
XX-M-080
Wolf Creek Generating Station Pump Room Heat-Up
Analysis
Corrective Action
Documents
Condition Reports
10001155, 10001305, 10001975, 10007983, 10010737,
10011933, 10012377, 10019061, 10016320, 10016321,
10016406, 10016449, 10017201, 10017205, 10017212,
10017625, 10020153
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10017443, 10017590, 10017591
Engineering
Changes
DCP 20390
Containment Purge Isolation Zone
Miscellaneous
2018-011
USAR Change Request
07/10/2018
Miscellaneous20-012
USAR Change Request
09/16/2020
Miscellaneous21-010
USAR Change Request
09/21/2021
Miscellaneous
ET 16-0017
Updated Response to Generic Letter 89-13
07/26/2016
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
Post Maintenance Testing Development
21A
Procedures
Heat Exchanger Program
Procedures
Operability Determination and Functionality Assessment
Procedures
EDI 23M-060
Engineering Desktop Instruction Performing Maintenance
Rule Periodic Assessments
Procedures
MPE RC-001
Room Cooler Maintenance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
MPM XX-002
Watertight Doors Preventive Maintenance Activity
7B
Procedures
OFN EF-033
Loss of Essential Service Water
Procedures
STN PE-036
Safety Related Room Cooler Heat Transfer Verification and
Performance Trending
16, 17
Procedures
STN PE-037B
ESW Train B Heat Exchanger Flow and DP Trending
Procedures
STS PE-004
Aux Building and Control Room Pressure Test
Procedures
STS PE-007
Periodic Verification of Motor Operated Valves
5A
Procedures
SYS PE-175
LLRT Valve Lineup for Penetration 75
Work Orders
2-362212-003, 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
Corrective Action
Documents
Condition Reports
10018514, 10018670, 10018671, 10018701, 10018757,
10018763, 10018910, 10019558, 10019604, 10019607,
10019608, 10019610, 10019613, 10019719, 10019741,
10019773
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10018198, 10018731, 10018890, 10020846
Drawings
KD-7496
One Line Diagram
Drawings
WIP-KD-2796-
073-B-1
One Line Diagram
Miscellaneous
APF 22B-001-09
Shutdown Risk Assessment No Mode - Defueled
Miscellaneous
APF 22B-001-10
Shutdown Safety Function Status and Assessment
Summary
Procedures
Outage Risk Management
Procedures
OFN EC-046
Fuel Pool Cooling and Cleanup Malfunctions
Procedures
STS KJ-011A
EDG NE01 24 Hour Run
Procedures
SYS EC-202
Staging Alternate Spent Fuel Pool Cooling
Work Orders
21-473967-000, 22-482773-000, 22-482773-001,
2-482773-002, 22-482773-003, 22-482773-004,
2-482793-000,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
59606-M-001
Design Minimum Wall Thickness Values for Piping Bends
and Elbows in Main Feedwater Piping Located in
Containment
Calculations
AN-99-019
Radiological Consequences of the Main Steam Line Break
Outside Containment
Corrective Action
Documents
Condition Report
96-0794, 2006-000188, 123051, 123932, 10018783,
10019400, 10019761, 10019779, 10019819, 10019926,
10020042, 10020303
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10019205, 10020411
Drawings
M-12AL
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Engineering
Changes
DECP 20617
Alternate IP Transducer for SG Atmospheric Relief Valves
Miscellaneous
USAR Change Request 98-138
11/20/1998
Miscellaneous
DRR 06-1350
Document Revision Request
Miscellaneous
EQSD-I
Equipment Qualification Design Basis Document
Miscellaneous
M-10AL
Auxiliary Feedwater System
Miscellaneous
PQE-J-601B-P02
Atmospheric Relief Valves GT25 I/P Transducer
Miscellaneous
WCRE-34
Fourth 10-year Interval Inservice Testing Basis Document
Procedures
AI 21-016
Operator Time Critical Actions Validation
21A
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG E-2
Faulted Steam Generator Isolation
24A
Procedures
EMG ES-03
SI Termination
Procedures
STS AL-201C
Turbine Driven Auxiliary Feedwater System Inservice Valve
Test
Procedures
SYS AL-120
Motor Driven or Turbine Driven AFW Pump Operations
Work Orders
21-472871-002, 21-474872-001, 21-474872-003,
2-482825-000
Calculations
20517.01-C-
001
Wolf Creek Generating Station Simplified Head Assembly
(SHA) Drop Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Reports
2003-3473, 10019193, 100005074
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10019243
Drawings
M-703-00054
Closure Head General Assembly
W16
Engineering
Changes
CCP 012962
Canopy Seal Clamp Assembly in Capped Latch Location
Engineering
Changes
CCP 07910
Canopy Seal Clamp Assembly for Spare Penetrations
Engineering
Changes
CCP 10132
Canopy Seal Clamp Installation on Penetration 10
Engineering
Changes
DCP 05017
Canopy Seal Clamp Assemblies
Engineering
Changes
DECP 020328
Spare CET Canopy Seal Clamp Documentation Update
Miscellaneous
DRR 22-0019
Document Revision Request FHP 02-007A
Miscellaneous
WCNOC-4
Report on Control of Heavy Loads
Procedures
FHP 02-0007D
Load Cell Set Up and Use
Procedures
FHP 02-007A
Reactor Vessel Closure Head Removal
Procedures
FHP 02-007B
Reactor Vessel Closure Head Installation
Procedures
MCM BB-007
Installation and Removal Canopy Seal Clamp Assemblies
(CSCA)
Work Orders
18-442877-008, 18-442486-000, 18-442486-001,
20-458773-000, 21-458773-001, 21-471334-000
Corrective Action
Documents
Condition Reports
10017597, 10018224, 10018279, 10018346, 10018353,
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
Procedure
Type
Designation
Description or Title
Revision or
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
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10019548
Drawings
E-13AE06
Schematic Diagram Main Feedwater Control Valves
Drawings
M-018-00586
P9826 Crankcase Vac Ejector Application
W04
Drawings
M-12AE01
Piping and Instrumentation Diagram Feedwater System
Drawings
M-12EJ01
Piping and Instrumentation Diagram Residual Heat Removal
System
Drawings
M-12EP01
Piping and Instrumentation Diagram Accumulator Safety
Injection
Engineering
Changes
CP 20662
Replacement Cap Screw for AEFV0041
Engineering
Changes
DCP 020292
Substation Transformer No. 8, 9, 10, & 11 and Breaker
Replacement R25
Engineering
Changes
DECP
Main Feedwater Reg Valve Body to Bonnet Stud Repair and
Chamfering of Existing Studs
Miscellaneous
BED
ESC Item 23 - MSIV ABHV0014 Discs Stelite Hardfacing
Cracks
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Procedures
Post Maintenance Testing Development
21A
Procedures
MEC-039
Emergency Diesel Engine Injection Nozzle Testing
Procedures
MPM KJ-006
Emergency Diesel Rocker Lube Oil Strainer Cleaning
Procedures
STS AE-205
Feedwater System Inservice Valve Test
Procedures
STS AE-207
Feed Reg Valve Inservice Valve Test
Procedures
STS CV-210A
ECCS SI Comprehensive Pump and Inservice Check Valve
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Testing
Procedures
STS IC-611A
Slave Relay Test K611 K612 K613 Train A Feedwater
Isolation
Procedures
STS KJ-001A
Integrated D/G and Safeguards Actuation Test - Train A
Procedures
SYS NB-202
Transferring NB02 Power Sources
Work Orders
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
Corrective Action
Documents
Condition Reports
10018507, 10018511, 10018513, 10018524, 10018580,
10018584, 10018637, 10018676, 10018695, 10018721,
10019038, 10019184, 10019693, 10019784, 10019791,
10019793, 10020031, 10020032, 10020346, 10020052
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10018622, 10019805, 10019923, 10020191, 10020192,
10020292, 10020293, 10020294, 10020295, 10020297
Procedures
GEN 00-005
Minimum Load to Hot Standby
Procedures
GEN 00-006
Hot Standby to Cold Shutdown
106
Procedures
GEN 00-008
RCS Level Less Than Reactor Vessel Flange Operations
Procedures
GEN 00-009
Refueling
Procedures
OFN BB-031
Shutdown LOCA
36A
Procedures
OFN EG-004
CCW System Malfunction
Procedures
OFN EJ-015
Loss of RHR Cooling
Procedures
OFN EJ-040
CL Recirc During Mode 3, with Accumulators Isolated,
Mode 4, 5, or 6
Procedures
STS BB-011
Reactor Coolant System and Pressurizer Heatup/Cooldown
Surveillance
Procedures
STS BG-001
Boron Injection Flow Path Verification
Procedures
STS CR-002
Shift Log for Modes 4, 5, and 6
Procedures
SYS EJ-120
Startup of a Residual Heat Removal Train
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
FD-13-007
Corrective Action
Documents
Condition Reports
10003430, 10003431, 10018003, 10018558, 10018559,
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
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10019820
Drawings
M-12EF02
Piping Instrumentation Diagram Essential Service Water
System
Miscellaneous
MS-01
Piping Class Summary
Miscellaneous
STRIDE 22-00
Wolf Creek (18 months) NK (125 VDC Class 1E) Batteries
Surveillance
Miscellaneous
WCNOC-182
Operations and Maintenance Manual Spent Fuel Pool
Makeup Pump
W02
Miscellaneous
WCNOC-186
Operations and Maintenance Manual Core Cooling Pump
W01
Miscellaneous
WCRE-34
WCNOC Fourth 10-Year Interval Inservice Testing Program
Miscellaneous
WCRE-38
Surveillance Frequency Control Program Surveillance Test
Interval List
Procedures
PRA Methodology for Evaluating Changes to Surveillance
Test Intervals
Procedures
Diverse and Flexible Coping Mitigation (FLEX) Program
3A
Procedures
AP 29-009
Surveillance Test Risk Informed Documented Evaluation
(STRIDE) Process
Procedures
AP 29-011
Surveillance Frequency Control Program
Procedures
Program Plan for Containment Leakage Measurements
Procedures
STS MT-021
Service Test for 125 VDC Class 1E Batteries
Procedures
STS MT-080
25 Volt DC Battery Inspection
Procedures
STS PE-018
Containment Integrated Leakage Rate Test
Procedures
STS PE-171
LLRT Valve Lineup for Penetrations 71 and 73
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STS PE-261
LLRT Valve Lineup for Penetration 161
Procedures
SYS GP-515
CILRT-EF System
Work Orders
21-476771-000, 22-476912-000, 22-476912-001
Corrective Action
Documents
Condition Reports
10002460, 10003015, 10003660, 10003789, 10003935,
10004384, 10004685, 10004833, 10012104, 10015213,
10016703, 10017231, 10017940, 10018158, 10018831,
10019497, 10019533, 10020039
Miscellaneous
21 RWP Budget vs Actuals (Outage/Non-Outage): Outage
March 25, 2021 through May 15, 2021
09/28/2022
Miscellaneous
22 ALARA and RWP Quick Look Report
09/12/2022
Miscellaneous
330342
Access Control Shift Log
10/18/2022
Procedures
Radiation Protection Manual
Procedures
Access to Locked High or Very High Radiation Areas
Procedures
ALARA Program
Procedures
Radiation Worker Guidelines
Procedures
RPP 02-105
RWP (Radiation Work Permits)
Procedures
RPP 02-205
Radiological Survey Frequency Requirements
Procedures
RPP 02-215
Posting of Radiological Controlled Areas
34B
Procedures
RPP 02-405
RCA Access Control
Procedures
RPP 02-515
Release of Material from the RCA
Procedures
RPP 07-212
Requirements of Radioactive Materials Stored Outdoors
Radiation
Surveys
2-0071
Airborne Radioactivity Record: Auxiliary Building 2000'
05/11/2022
Radiation
Surveys
2-0072
Airborne Radioactivity Record: Auxiliary Building 2000'
05/11/2022
Radiation
Surveys
2-0170
Airborne Radioactivity Record: Fuel Building 2047' and
above
08/22/2022
Radiation
Surveys
2-0174
Airborne Radioactivity Record: Fuel Building 2047' and
above
08/22/2022
Radiation
Surveys
M-20220719-8
Demin alley
07/19/2022
Radiation
Surveys
M-20221018-42
2000' CTMT "D" Loop, BB8949D Dose rate alarm follow-up
10/18/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
M-20221030-3
CTMT B/C Secondary follow-up for dose rate alarm
10/30/2022
Radiation
Surveys
M-20221101-2
Letdown Cubicle
11/01/2022
Radiation
Surveys
RT Work Order:
20-462202-007
Radiography posting and guarding locations in containment
11/01/2022
Radiation Work
Permits (RWPs)
20020
Waste processing activities, cartridge filter change out, and
resin transfer
Radiation Work
Permits (RWPs)
21102
In-core Tunnel Inspections, Maintenance and
Decontamination
Radiation Work
Permits (RWPs)
2000
Mechanical Maintenance activities
Radiation Work
Permits (RWPs)
2601
Routine Access
Radiation Work
Permits (RWPs)
23021
Radiography activities
Radiation Work
Permits (RWPs)
24461
Motor Operated Valves Team activities.
Radiation Work
Permits (RWPs)
26020
Reactor Vessel Head Lift Preparation and Post Head Set
Work Activities
Radiation Work
Permits (RWPs)
26050
Reactor Vessel Upper Internals removal, transfer, and
replacement
Radiation Work
Permits (RWPs)
26060
Fuel Movement and Related Support Activities
Self-Assessments 22-01-RP/C
Quality Assurance Standard Audit Checklist:
Radiological Protection & Process Control
01/20/2022
Corrective Action
Documents
Condition Reports
10006532, 10009497, 10009726, 10015620, 10016405
Miscellaneous
Site Air Sample Logs: April 1, 2021 - September 13, 2022
Miscellaneous
20 ANI Nuclear Liability Insurance Inspection Response
03/31/2021
Miscellaneous
Trace Analytics, Certificates of Analysis - January 19, 2021
through October 22, 2022
Miscellaneous
AIF 10-001-02
Monthly SCBA Inspections - May 2021 through September
22
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
K15-002 22-01-
RP/PC
Quality Assurance Standard Audit Checklist - Radiological
Protection & Process Control: January 10 - January 20, 2022
01/20/2022
Miscellaneous
STS PE-002-
FGG02A
Charcoal Adsorbent Sampling for Nuclear Safety Related
Units - FGG02A
07/06/2022
Miscellaneous
STS PE-002-
FGG02B
Charcoal Adsorbent Sampling for Nuclear Safety Related
Units - FGG02B
08/23/2022
Miscellaneous
STS PE-005-
FGG02B
HEPA Filter In-Place Leak Test Safety Related Units -
FGG02B
08/15/2022
Miscellaneous
STS PE-006-
FGG02B
Charcoal Adsorber In-Place Leak Test Safety Related Units -
FGG02B
08/15/2022
Miscellaneous
STS PE-006-
FGK02B
Charcoal Adsorber In-Place Leak Test Safety Related Units -
FGK02B
03/03/2022
Miscellaneous
STS-PE-005-
FGK01B
HEPA Filter In-Place Leak Test Safety Related Units -
FGK01B
2/21/2022
Procedures
AI 10-004
Air Fill Station Operation
4A
Procedures
AI 14-009
Industrial Respiratory Protection Program
Procedures
Radiation Worker Guidelines
Procedures
MCE CF-001
Filtration Units Bulk Spent Charcoal Changeout
1A
Procedures
MCE CF-002
Filtration Unit Spent Charcoal Tray Replacement
Procedures
RPP 05-607
Operation of the Portacount
14A
Procedures
STS PE-002
Charcoal Adsorbent Sampling for Nuclear Safety Related
Units
Procedures
STS PE-005
HEPA Filter In-Place Leak Test Safety Related Units
Procedures
STS PE-006
Charcoal Adsorber In-Place Leak Test Safety Related Units
Radiation Work
Permits (RWPs)
20061
Fuel Building Transfer Canal Entry for Repair/Inspection and
Decon of Fuel Building Transfer System.
71151
Miscellaneous
21 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
71152A
Corrective Action
Documents
Condition Reports
20499, 96405, 99718, 10011538, 10019657, 10020251,
10020290, 10020304
71152A
Procedures
Closed Cooling Water Chemistry Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152A
Work Orders
19-456413-000
71152S
Corrective Action
Documents
Condition Reports
10013158, 10013210, 10013236, 10013254, 10014124,
10014211, 10014212, 10014598, 10014599, 10014600,
10014601, 10014602, 10014603, 10018450, 10020738,
10020739, 10020740, 10020741, 10020742, 10020743,
10020770, 10020771
71152S
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10021065
71152S
Miscellaneous
2-05-EP
Quality Assurance Audit Report (Emergency Preparedness)
06/06/2022
71152S
Miscellaneous
SA-2021-0171
EP Program and PI Self-Assessment
03/24/2022
Corrective Action
Documents
Condition Reports
10019281, 10019287, 10019604, 10019607, 10019608,
10019610, 10019613
Procedures
OFN EF-033
Loss of Essential Service Water
24