IR 05000482/2022004

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Integrated Inspection Report 05000482/2022004
ML23011A089
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
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

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

71111.01

Procedures

AI 14-006

Severe Weather

71111.01

Procedures

AP 21C-001

Wolf Creek Substation

71111.01

Procedures

AP 22B-001

Outage Risk Management

71111.01

Procedures

OFN SG-003

Natural Events

71111.04

Corrective Action

Documents

Condition Reports

10019036, 10019635, 10019638

71111.04

Drawings

DK-7496

One Line Diagram

71111.04

Procedures

OFN AF-025

Unit Limitations

71111.04

Procedures

SYS NB-200

Transferring XNB01 Supply Between #8 Transformer and #9

Transformer Using NE01

71111.04

Procedures

SYS SL-204

Transferring Bus 13.8 kV Supplies Between XFMR #8/10

and #9/11

71111.05

Corrective Action

Documents

Condition Report

10018713, 10013103, 10017895

71111.05

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10018526

71111.05

Miscellaneous

10013103 - Root

Cause Analysis

10013103 - Root Cause Analysis for Missed Fire Watch

Checks

71111.05

Miscellaneous

E-1F9910

Post Fire Safe Shutdown Area Analysis

71111.05

Procedures

AP 10-106

Fire Preplans

71111.08P

Calculations

W-SMT-95-100

Westinghouse Analysis for SI Hot Leg Loop 2 & 3 Snubber

Analysis - Reactor Building

71111.08P

Calibration

Records

WC014912

Calibration of Various Force Indicating Devices:

Dynamometer (Dillon) AP D901837

2/23/2022

71111.08P

Calibration

Records

WC019104

Calibration of Various Force Indicating Devices:

Dynamometer (Dillon) D D-22156

2/23/2022

71111.08P

Calibration

Records

WC019105

Calibration of Various Force Indicating Devices:

Dynamometer (Dillon) D D-22155

05/24/2022

71111.08P

Corrective Action

Documents

CR 10018557

Boric Acid Residue RBB01 top head

10/16/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.08P

Corrective Action

Documents

CR 10018704

EMV0110 Dry White Boron Leakage from Packing

10/18/2022

71111.08P

Corrective Action

Documents

CR 10018704

EMV0110 Dry White Boron Leakage from Packing

10/18/2022

71111.08P

Corrective Action

Documents

Resulting from

Inspection

CR 10018949

EMV0110 Dried White Boron Accumulation

10/20/2022

71111.08P

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)

71111.08P

Miscellaneous

WCRE-30

Inservice Inspection Program Plan - Wolf Creek Generating

Station - Interval 4

71111.08P

NDE Reports

180-9326103-000

Framatome NDE Services Final Report: Wolf Creek Unit 1 -

RF24 RVCH Penetration Examination Report

04/18/2021

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

71111.08P

Procedures

AP 15C-004

Preparation, Review and Approval of Procedures,

Instructions and Forms

55A

71111.08P

Procedures

AP 16F-001

Boric Acid Corrosion Control Program

10A

71111.08P

Procedures

LMT-08-MT-01

Magnetic Particle Examination

71111.08P

Procedures

LMT-08-UT-004

Ultrasonic Examination of Vessel Welds and Adjacent Base

Metal >2" in Thickness

71111.08P

Procedures

STS PE-040E

RPV Head Visual Inspection

71111.08P

Work Orders

WO 18-445398-

SI Accum to Loop 1 Check Valve (BB8948A). Westinghouse

Calculation allows pipe to be cold sprung

10/21/2022

71111.08P

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

71111.08P

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

71111.08P

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.

71111.11Q

Procedures

EMG E-0

Reactor Trip or Safety Injection

71111.11Q

Procedures

GEN 00-004

Power Operation

101

71111.12

Calculations

XX-M-080

Wolf Creek Generating Station Pump Room Heat-up

Analysis

71111.12

Calculations

DEB

Blocked Tubes on SGL09B - CR 10015041

71111.12

Calculations

EG-M-055

Overload Evaluation for Anchor-Darling Double-Disc Wedge

Gate Valve

71111.12

Calculations

GL-M-007

Calculate Cooling Load in SR Pump Rooms Post LOCA:

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

Analysis

71111.12

Corrective Action

Documents

Condition Reports

10001155, 10001305, 10001975, 10007983, 10010737,

10011933, 10012377, 10019061, 10016320, 10016321,

10016406, 10016449, 10017201, 10017205, 10017212,

10017625, 10020153

71111.12

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10017443, 10017590, 10017591

71111.12

Engineering

Changes

DCP 20390

Containment Purge Isolation Zone

71111.12

Miscellaneous

2018-011

USAR Change Request

07/10/2018

71111.12

Miscellaneous20-012

USAR Change Request

09/16/2020

71111.12

Miscellaneous21-010

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

71111.12

Procedures

AP 16E-002

Post Maintenance Testing Development

21A

71111.12

Procedures

AP 23L-002

Heat Exchanger Program

71111.12

Procedures

AP 26C-004

Operability Determination and Functionality Assessment

71111.12

Procedures

EDI 23M-060

Engineering Desktop Instruction Performing Maintenance

Rule Periodic Assessments

71111.12

Procedures

MPE RC-001

Room Cooler Maintenance

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.12

Procedures

MPM XX-002

Watertight Doors Preventive Maintenance Activity

7B

71111.12

Procedures

OFN EF-033

Loss of Essential Service Water

71111.12

Procedures

STN PE-036

Safety Related Room Cooler Heat Transfer Verification and

Performance Trending

16, 17

71111.12

Procedures

STN PE-037B

ESW Train B Heat Exchanger Flow and DP Trending

71111.12

Procedures

STS PE-004

Aux Building and Control Room Pressure Test

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

71111.12

Work Orders

WO

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

71111.13

Corrective Action

Documents

Condition Reports

10018514, 10018670, 10018671, 10018701, 10018757,

10018763, 10018910, 10019558, 10019604, 10019607,

10019608, 10019610, 10019613, 10019719, 10019741,

10019773

71111.13

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10018198, 10018731, 10018890, 10020846

71111.13

Drawings

KD-7496

One Line Diagram

71111.13

Drawings

WIP-KD-2796-

073-B-1

One Line Diagram

71111.13

Miscellaneous

APF 22B-001-09

Shutdown Risk Assessment No Mode - Defueled

71111.13

Miscellaneous

APF 22B-001-10

Shutdown Safety Function Status and Assessment

Summary

71111.13

Procedures

AP 22B-001

Outage Risk Management

71111.13

Procedures

OFN EC-046

Fuel Pool Cooling and Cleanup Malfunctions

71111.13

Procedures

STS KJ-011A

EDG NE01 24 Hour Run

71111.13

Procedures

SYS EC-202

Staging Alternate Spent Fuel Pool Cooling

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Calculations

59606-M-001

Design Minimum Wall Thickness Values for Piping Bends

and Elbows in Main Feedwater Piping Located in

Containment

71111.15

Calculations

AN-99-019

Radiological Consequences of the Main Steam Line Break

Outside Containment

71111.15

Corrective Action

Documents

Condition Report

96-0794, 2006-000188, 123051, 123932, 10018783,

10019400, 10019761, 10019779, 10019819, 10019926,

10020042, 10020303

71111.15

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10019205, 10020411

71111.15

Drawings

M-12AL

Piping and Instrumentation Diagram Auxiliary Feedwater

System

71111.15

Engineering

Changes

DECP 20617

Alternate IP Transducer for SG Atmospheric Relief Valves

71111.15

Miscellaneous

USAR Change Request 98-138

11/20/1998

71111.15

Miscellaneous

DRR 06-1350

Document Revision Request

71111.15

Miscellaneous

EQSD-I

Equipment Qualification Design Basis Document

71111.15

Miscellaneous

M-10AL

Auxiliary Feedwater System

71111.15

Miscellaneous

PQE-J-601B-P02

Atmospheric Relief Valves GT25 I/P Transducer

71111.15

Miscellaneous

WCRE-34

Fourth 10-year Interval Inservice Testing Basis Document

71111.15

Procedures

AI 21-016

Operator Time Critical Actions Validation

21A

71111.15

Procedures

EMG E-0

Reactor Trip or Safety Injection

71111.15

Procedures

EMG E-2

Faulted Steam Generator Isolation

24A

71111.15

Procedures

EMG ES-03

SI Termination

71111.15

Procedures

STS AL-201C

Turbine Driven Auxiliary Feedwater System Inservice Valve

Test

71111.15

Procedures

SYS AL-120

Motor Driven or Turbine Driven AFW Pump Operations

71111.15

Work Orders

WO

21-472871-002, 21-474872-001, 21-474872-003,

2-482825-000

71111.18

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

71111.18

Corrective Action

Documents

Condition Reports

2003-3473, 10019193, 100005074

71111.18

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10019243

71111.18

Drawings

M-703-00054

Closure Head General Assembly

W16

71111.18

Engineering

Changes

CCP 012962

Canopy Seal Clamp Assembly in Capped Latch Location

71111.18

Engineering

Changes

CCP 07910

Canopy Seal Clamp Assembly for Spare Penetrations

71111.18

Engineering

Changes

CCP 10132

Canopy Seal Clamp Installation on Penetration 10

71111.18

Engineering

Changes

DCP 05017

Canopy Seal Clamp Assemblies

71111.18

Engineering

Changes

DECP 020328

Spare CET Canopy Seal Clamp Documentation Update

71111.18

Miscellaneous

DRR 22-0019

Document Revision Request FHP 02-007A

71111.18

Miscellaneous

WCNOC-4

Report on Control of Heavy Loads

71111.18

Procedures

FHP 02-0007D

Load Cell Set Up and Use

71111.18

Procedures

FHP 02-007A

Reactor Vessel Closure Head Removal

71111.18

Procedures

FHP 02-007B

Reactor Vessel Closure Head Installation

71111.18

Procedures

MCM BB-007

Installation and Removal Canopy Seal Clamp Assemblies

(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

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

71111.19

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10019548

71111.19

Drawings

E-13AE06

Schematic Diagram Main Feedwater Control Valves

71111.19

Drawings

M-018-00586

P9826 Crankcase Vac Ejector Application

W04

71111.19

Drawings

M-12AE01

Piping and Instrumentation Diagram Feedwater System

71111.19

Drawings

M-12EJ01

Piping and Instrumentation Diagram Residual Heat Removal

System

71111.19

Drawings

M-12EP01

Piping and Instrumentation Diagram Accumulator Safety

Injection

71111.19

Engineering

Changes

CP 20662

Replacement Cap Screw for AEFV0041

71111.19

Engineering

Changes

DCP 020292

Substation Transformer No. 8, 9, 10, & 11 and Breaker

Replacement R25

71111.19

Engineering

Changes

DECP

Main Feedwater Reg Valve Body to Bonnet Stud Repair and

Chamfering of Existing Studs

71111.19

Miscellaneous

BED

ESC Item 23 - MSIV ABHV0014 Discs Stelite Hardfacing

Cracks

71111.19

Miscellaneous

WCRE-34

Fourth 10-Year Interval Inservice Testing Basis Document

71111.19

Procedures

AP 16E-002

Post Maintenance Testing Development

21A

71111.19

Procedures

MEC-039

Emergency Diesel Engine Injection Nozzle Testing

71111.19

Procedures

MPM KJ-006

Emergency Diesel Rocker Lube Oil Strainer Cleaning

71111.19

Procedures

STS AE-205

Feedwater System Inservice Valve Test

71111.19

Procedures

STS AE-207

Feed Reg Valve Inservice Valve Test

71111.19

Procedures

STS CV-210A

ECCS SI Comprehensive Pump and Inservice Check Valve

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Testing

71111.19

Procedures

STS IC-611A

Slave Relay Test K611 K612 K613 Train A Feedwater

Isolation

71111.19

Procedures

STS KJ-001A

Integrated D/G and Safeguards Actuation Test - Train A

71111.19

Procedures

SYS NB-202

Transferring NB02 Power Sources

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

Documents

Condition Reports

10018507, 10018511, 10018513, 10018524, 10018580,

10018584, 10018637, 10018676, 10018695, 10018721,

10019038, 10019184, 10019693, 10019784, 10019791,

10019793, 10020031, 10020032, 10020346, 10020052

71111.20

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10018622, 10019805, 10019923, 10020191, 10020192,

10020292, 10020293, 10020294, 10020295, 10020297

71111.20

Procedures

GEN 00-005

Minimum Load to Hot Standby

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

71111.20

Procedures

GEN 00-009

Refueling

71111.20

Procedures

OFN BB-031

Shutdown LOCA

36A

71111.20

Procedures

OFN EG-004

CCW System Malfunction

71111.20

Procedures

OFN EJ-015

Loss of RHR Cooling

71111.20

Procedures

OFN EJ-040

CL Recirc During Mode 3, with Accumulators Isolated,

Mode 4, 5, or 6

71111.20

Procedures

STS BB-011

Reactor Coolant System and Pressurizer Heatup/Cooldown

Surveillance

71111.20

Procedures

STS BG-001

Boron Injection Flow Path Verification

71111.20

Procedures

STS CR-002

Shift Log for Modes 4, 5, and 6

71111.20

Procedures

SYS EJ-120

Startup of a Residual Heat Removal Train

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.22

Calculations

FD-13-007

AFW FLEX Hydraulic Evaluation

71111.22

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

71111.22

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10019820

71111.22

Drawings

M-12EF02

Piping Instrumentation Diagram Essential Service Water

System

71111.22

Miscellaneous

MS-01

Piping Class Summary

71111.22

Miscellaneous

STRIDE 22-00

Wolf Creek (18 months) NK (125 VDC Class 1E) Batteries

Surveillance

71111.22

Miscellaneous

WCNOC-182

Operations and Maintenance Manual Spent Fuel Pool

Makeup Pump

W02

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

71111.22

Miscellaneous

WCRE-38

Surveillance Frequency Control Program Surveillance Test

Interval List

71111.22

Procedures

AP 05C-005

PRA Methodology for Evaluating Changes to Surveillance

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

(STRIDE) Process

71111.22

Procedures

AP 29-011

Surveillance Frequency Control Program

71111.22

Procedures

AP 29E-001

Program Plan for Containment Leakage Measurements

71111.22

Procedures

STS MT-021

Service Test for 125 VDC Class 1E Batteries

71111.22

Procedures

STS MT-080

25 Volt DC Battery Inspection

71111.22

Procedures

STS PE-018

Containment Integrated Leakage Rate Test

71111.22

Procedures

STS PE-171

LLRT Valve Lineup for Penetrations 71 and 73

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.22

Procedures

STS PE-261

LLRT Valve Lineup for Penetration 161

71111.22

Procedures

SYS GP-515

CILRT-EF System

71111.22

Work Orders

WO

21-476771-000, 22-476912-000, 22-476912-001

71124.01

Corrective Action

Documents

Condition Reports

10002460, 10003015, 10003660, 10003789, 10003935,

10004384, 10004685, 10004833, 10012104, 10015213,

10016703, 10017231, 10017940, 10018158, 10018831,

10019497, 10019533, 10020039

71124.01

Miscellaneous

21 RWP Budget vs Actuals (Outage/Non-Outage): Outage

March 25, 2021 through May 15, 2021

09/28/2022

71124.01

Miscellaneous

22 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

71124.01

Procedures

AP 25A-200

Access to Locked High or Very High Radiation Areas

71124.01

Procedures

AP 25A-401

ALARA Program

71124.01

Procedures

AP 25B-100

Radiation Worker Guidelines

71124.01

Procedures

RPP 02-105

RWP (Radiation Work Permits)

71124.01

Procedures

RPP 02-205

Radiological Survey Frequency Requirements

71124.01

Procedures

RPP 02-215

Posting of Radiological Controlled Areas

34B

71124.01

Procedures

RPP 02-405

RCA Access Control

71124.01

Procedures

RPP 02-515

Release of Material from the RCA

71124.01

Procedures

RPP 07-212

Requirements of Radioactive Materials Stored Outdoors

71124.01

Radiation

Surveys

2-0071

Airborne Radioactivity Record: Auxiliary Building 2000'

05/11/2022

71124.01

Radiation

Surveys

2-0072

Airborne Radioactivity Record: Auxiliary Building 2000'

05/11/2022

71124.01

Radiation

Surveys

2-0170

Airborne Radioactivity Record: Fuel Building 2047' and

above

08/22/2022

71124.01

Radiation

Surveys

2-0174

Airborne Radioactivity Record: Fuel Building 2047' and

above

08/22/2022

71124.01

Radiation

Surveys

M-20220719-8

Demin alley

07/19/2022

71124.01

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

71124.01

Radiation

Surveys

M-20221030-3

CTMT B/C Secondary follow-up for dose rate alarm

10/30/2022

71124.01

Radiation

Surveys

M-20221101-2

Letdown Cubicle

11/01/2022

71124.01

Radiation

Surveys

RT Work Order:

20-462202-007

Radiography posting and guarding locations in containment

11/01/2022

71124.01

Radiation Work

Permits (RWPs)

20020

Waste processing activities, cartridge filter change out, and

resin transfer

71124.01

Radiation Work

Permits (RWPs)

21102

In-core Tunnel Inspections, Maintenance and

Decontamination

71124.01

Radiation Work

Permits (RWPs)

2000

Mechanical Maintenance activities

71124.01

Radiation Work

Permits (RWPs)

2601

Routine Access

71124.01

Radiation Work

Permits (RWPs)

23021

Radiography activities

71124.01

Radiation Work

Permits (RWPs)

24461

Motor Operated Valves Team activities.

71124.01

Radiation Work

Permits (RWPs)

26020

Reactor Vessel Head Lift Preparation and Post Head Set

Work Activities

71124.01

Radiation Work

Permits (RWPs)

26050

Reactor Vessel Upper Internals removal, transfer, and

replacement

71124.01

Radiation Work

Permits (RWPs)

26060

Fuel Movement and Related Support Activities

71124.01

Self-Assessments 22-01-RP/C

Quality Assurance Standard Audit Checklist:

Radiological Protection & Process Control

01/20/2022

71124.03

Corrective Action

Documents

Condition Reports

10006532, 10009497, 10009726, 10015620, 10016405

71124.03

Miscellaneous

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

71124.03

Miscellaneous

20 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

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.03

Miscellaneous

K15-002 22-01-

RP/PC

Quality Assurance Standard Audit Checklist - Radiological

Protection & Process Control: January 10 - January 20, 2022

01/20/2022

71124.03

Miscellaneous

STS PE-002-

FGG02A

Charcoal Adsorbent Sampling for Nuclear Safety Related

Units - FGG02A

07/06/2022

71124.03

Miscellaneous

STS PE-002-

FGG02B

Charcoal Adsorbent Sampling for Nuclear Safety Related

Units - FGG02B

08/23/2022

71124.03

Miscellaneous

STS PE-005-

FGG02B

HEPA Filter In-Place Leak Test Safety Related Units -

FGG02B

08/15/2022

71124.03

Miscellaneous

STS PE-006-

FGG02B

Charcoal Adsorber In-Place Leak Test Safety Related Units -

FGG02B

08/15/2022

71124.03

Miscellaneous

STS PE-006-

FGK02B

Charcoal Adsorber In-Place Leak Test Safety Related Units -

FGK02B

03/03/2022

71124.03

Miscellaneous

STS-PE-005-

FGK01B

HEPA Filter In-Place Leak Test Safety Related Units -

FGK01B

2/21/2022

71124.03

Procedures

AI 10-004

Air Fill Station Operation

4A

71124.03

Procedures

AI 14-009

Industrial Respiratory Protection Program

71124.03

Procedures

AP 25B-100

Radiation Worker Guidelines

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

71124.03

Procedures

RPP 05-607

Operation of the Portacount

14A

71124.03

Procedures

STS PE-002

Charcoal Adsorbent Sampling for Nuclear Safety Related

Units

71124.03

Procedures

STS PE-005

HEPA Filter In-Place Leak Test Safety Related Units

71124.03

Procedures

STS PE-006

Charcoal Adsorber In-Place Leak Test Safety Related Units

71124.03

Radiation Work

Permits (RWPs)

20061

Fuel Building Transfer Canal Entry for Repair/Inspection and

Decon of Fuel Building Transfer System.

71151

Miscellaneous

RA 22-0038

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

AP 02B-002

Closed Cooling Water Chemistry Control

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152A

Work Orders

WO

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

71153

Corrective Action

Documents

Condition Reports

10019281, 10019287, 10019604, 10019607, 10019608,

10019610, 10019613

71153

Procedures

OFN EF-033

Loss of Essential Service Water

24