IR 05000482/2019004
| ML20035C736 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/03/2020 |
| From: | O'Keefe N NRC/RGN-IV/DRP/RPB-B |
| To: | Reasoner C Wolf Creek |
| References | |
| EPID L-2019-004-0012 IR 2019004 | |
| Preceding documents: |
|
| Download: ML20035C736 (32) | |
Text
February 3, 2020
SUBJECT:
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2019004
Dear Mr. Reasoner:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On January 9, 2020, the NRC inspectors discussed the results of this inspection with Mr. J. McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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,
/RA Russell L. Bywater Acting for/
Neil F. O'Keefe, Chief Reactor Projects Branch B Division of Reactor Projects
Docket No. 05000482 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier: I-2019-004-0012
Licensee:
Wolf Creek Nuclear Operating Corporation
Facility:
Wolf Creek Generating Station
Location:
Burlington, KS 66839
Inspection Dates:
October 1, 2019, to December 31, 2019
Inspectors:
D. Dodson, Senior Resident Inspector
C. Alldredge, Allegations/Enforcement Specialist
I. Anchondo-Lopez, Reactor Inspector
R. Azua, Inspection Programs & Assessment Team Leader
B. Baca, Resident Inspector
R. Bywater, Acting Senior Project Engineer
P. Elkmann, Senior Emergency Preparedness Inspector
S. Hedger, Emergency Preparedness Inspector
P. Jayroe, Reactor Inspector
J. Melfi, Project Engineer
A. Meyen, Physical Security Inspector
W. Sifre, Senior Reactor Inspector
M. Stafford, Acting Senior Resident Inspector
F. Thomas, Reactor Inspector
J. Vera, Resident Inspector
Approved By:
Neil F. O'Keefe, Chief
Reactor Projects Branch B
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000482/2017-003-00
[Atmospheric Relief Valve] and
[Main Steam Safety Valve]
Tornado Missile Vulnerabilities Result in Unanalyzed Condition 71153 Discussed LER 05000482/2019-001-00 Loss of Startup Transformer Results in Emergency Diesel Generator Actuation 71153 Closed LER 05000482/2019-002-00 Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure 71153 Closed
PLANT STATUS
Wolf Creek Generating Station began the inspection period shutdown for Refueling Outage 23. The reactor was restarted on November 5, 2019, and power ascension was commenced. The unit was returned to approximately rated thermal power on November 9, 2019, and remained at or near rated thermal power for the remainder of the inspection 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
- Essential service water
- Refueling water storage tank
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Component cooling water train A on October 3, 2019
- (2) Spent fuel pool cooling train B on November 18, 2019
- (3) Containment purge system on December 27, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the residual heat removal system on November 8, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Auxiliary building, elevation 1,974 feet, fire areas A-2 and A-3, on October 2, 2019
- (2) Essential service water vertical loop chase, elevation 1,974 feet through 2,087 feet, fire area ESWC, on November 29, 2019
- (3) Auxiliary building, elevation 2,026 feet, fire areas A-17 and A-18, on December 30, 2019
- (4) Essential service water pump house, elevation 2,000 feet, fire areas ESWA and ESWB, on December 31, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Residual heat removal pump A room on October 10, 2019
- (2) Spent fuel pool cooling train B room on October 17, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Component cooling water heat exchanger train B on October 24, 2019
===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 September 28, 2019, to October 3, 2019:
03.01.a - Nondestructive Examination and Welding Activities
- Ultrasonic examination, main feedwater loop 2, AE-4S026-A pipe to elbow
- Ultrasonic examination, main feedwater loop 2, AE-4S026-B elbow to pipe
- Ultrasonic examination, residual heat removal A, EJ-01-S017-F pipe to elbow
- Ultrasonic examination, residual heat removal A, EJ-01-S017-B pipe to tee
- Ultrasonic examination, residual heat removal A, EJ-01-S017-D tee to pipe
- Ultrasonic examination, residual heat removal A, EJ-01-S017-G elbow to pipe
- Radiographic examination, boron thermal regeneration, 17-434419-004 pipe to pipe
- Dye penetrant, boron injection, EM-02-R008, pipe to pipe
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
- Visual examination of reactor head penetrations 1 through 79
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities
- The inspector reviewed the following work orders associated with boric acid leaks: 19-453764-000, 19-453325-000, 19-453324-000, 19-453323-000, 19-
===451840-000, and 19-451734-000.
03.01.d - No steam generator tube inspections were performed this inspection period.
03.01.e - Problem Identification and Resolution
- The inspector reviewed 31 condition reports associated with inservice and operating experience issues and concluded that nondestructive evaluation/inservice inspection related issues and operating experience are put into the corrective action program at a low threshold to ensure conditions and problems are 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) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup on November 5, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated just-in-time training for reactor startup on October 24, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Station blackout diesel generator control failure sample completed on October 23, 2019
- (2) Residual heat removal system performance review completed on October 25, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Planned essential service water train B maintenance during the refueling outage on October 7, 2019
- (2) Planned train swap activity control during the refueling outage on October 11, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (7 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Boric acid leak from normal charging check valve on October 21, 2019
- (2) Essential service water train B traveling screen elevated vibrations on October 22, 2019
- (3) Fuel assembly containing foreign material on October 24, 2019
- (4) Digital rod position indication alarms prior to reactor restart on October 27, 2019
- (5) Component cooling water to rad waste relief valve failed as found/as left tests on November 4, 2019
- (6) Load shedder and emergency load sequencer testing methodology questions identified on October 18, 2019
- (7) Main steam isolation action circuitry issue on November 7, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post-maintenance tests:
- (1) Emergency diesel generator train B post-maintenance testing following outage maintenance on October 10, 2019
- (2) Component cooling water heat exchanger train B following eddy current testing on October 18, 2019
- (3) Emergency diesel generator train A post-maintenance testing following outage maintenance on October 18, 2019
- (4) Component cooling water train B check valve post-maintenance testing on October 20, 2019
- (5) Essential service water train B post maintenance testing activities on October 22, 2019
- (6) Residual heat removal train B post-maintenance valve testing on October 22, 2019
- (7) Containment cooler B post maintenance testing on October 27, 2019
- (8) South electrical penetration room cooler post-maintenance testing on December 30, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Refueling Outage 23 activities from October 1 to November 6, 2019. The inspectors completed IP Sections 03.01.c, 03.01.d, and 03.01.e.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) STS-KJ-001A, Integrated [Diesel Generator] and Safeguards Actuation Test - Train A, Revision 65, on October 29, 2019, and STS-KJ-001B, Integrated [Diesel Generator] and Safeguards Actuation Test - Train B, Revision 63, on October 30, 2019
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) Train B essential service water vertical loop vacuum breaker valves (EF-V482 and EF-V484) inservice testing in accordance with STS KJ-001B, Integrated [Diesel Generator] and Safeguards Actuation Test - Train B, Revision 63, on October 29, 2019
- (2) STS EF-100A, "[Essential Service Water] System Inservice Pump A & [Essential Service Water] A Check Valve Test," Revision 47, on November 2, 2019
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) STS PE-125, "[Local Leak Rate Test] Valve Lineup for Penetration 25," Revision 9, on October 17, 2019
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise conducted December 3, 2019. The exercise scenario simulated two seismic events, losses of vital safety-related electric buses, a partial loss of offsite power, a loss of coolant accident inside containment, and a containment penetration failure causing a filtered and monitored radiological release through the plant vent. The inspectors also observed the licensee's management critique on December 17, 2019, and participated at the Federal Emergency Management Agency Region VII public meeting conducted on December 6, 2019. The inspectors discussed the performance of the licensee emergency response organization and offsite responders with Federal Emergency Management Agency Region VII staff on December 6, 2019.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the Wolf Creek Radiological Emergency Response Plan, Revision 19, on December 4, 2019, and Revision 20, on December 11, 2019. These evaluations do not constitute NRC approval.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors reviewed the following:
Radiological Surveys
- Survey M-20190921-5, "Downpost Survey for Upper Cavity"
- Survey M-20190924-21, "Bottom Mounted Instrumentation (BMI) Inspection,"
Under Vessel
- Survey M-20190926-14, "Core Exit Thermocouple Nozzle Assembly (CETNA)
Removal"
- Survey M-20190927-25, "Refueling (RF) 23 Reactor Head Lift"
- Survey M-20190930-3, "Valve Removal EM-V0212"
- Survey M-20190930-22, "Reactor Head on Head Stand"
- Survey M-20191002-18, "2047' Containment Weekly for Wednesday"
- Survey M-20191002-36, "B Residual Heat Removal (RHR) Pump Room - Lead and Insulation Removal"
- Survey M-20191003-14, "RadWaste Filter Change FEC01A"
Risk Significant Radiological Work Activities
- Fuel building transfer canal entries for repair/inspection and decontamination activities
- Radwaste filter change FEC01A
- Reactor head lift
- Reactor cavity activities
- Under reactor vessel cavity ring and incore tunnel inspections
Air Sample Survey Records
- Air Sample 19-0045, "Aux Building 2000' Filter (FBG06) Change Out"
- Air Sample 19-0134, "Post Maintenance Survey inside Transfer Canal 2047' Fuel Building"
- Air Sample 19-0143, "Grinding on SJHV0133 North Pipe Pen, Aux Building 2000' elevation"
- Air Sample 19-0254, "B Residual Heat Removal Pump Boric Acid Clean Up"
- Radwaste building filter pits
- Train B safety injection pump room for EM-V0212 valve removal
- Refueling outage (RF) 23 reactor head lift
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- Radiation Work Permit 190051, "Access to High Radiation Areas and Locked High Radiation Areas for Contaminated System Breaches and Boron Removal," Revision 1
- Radiation Work Permit 190061, "Fuel Building Transfer Canal Entry for Repair/Inspection and Decontamination of Fuel Building Transfer System and other work activities," Revision 1
- Radiation Work Permit 191101, "Under Reactor Vessel (RV) Cavity Seal Ring Inspections (Annulus) Access," Revision 0
- Radiation Work Permit 191102, "Incore Tunnel Inspections, Maintenance &
Decontamination," Revision 0
- Radiation Work Permit 195001, "Reactor Cavity Decon Activities," Revision 0
- Radiation Work Permit 196000, "Lower Refueling Cavity Pre & Post Flooding Maintenance Activities," Revision 1
Electronic Alarming Dosimeter Alarms The inspectors reviewed the licensee's corrective action program and selected five condition reports and associated documentation regarding electronic alarming dosimeter alarms for additional review:
- Condition Report 120680
- Condition Report 120975
- Condition Report 121726
- Condition Report 124071
- Condition Report 131088
Labeling of Containers
- Four radioactive material trash bags
- Six barrels of steam generator sludge lancing material and TriNuke filters and hoses
- Six Westinghouse refueling equipment boxes
- Two dry active waste sealand containers
Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and are intact:
- 98-CHL-041
- 00-HPL-009
- 03-HPL-028
- 82-HPL-088/82-HPL-089
- 84-HPL-326
- 92-HPL-009
Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors also reviewed the following radiological work package for areas with airborne radioactivity:
- Radiation Work Permit 190050, "No High Radiation Area (HRA),
Contaminated Systems Valve and Pump RWP," Revision 1
- Radiation Work Permit 190061, "Fuel Building Transfer Canal Entry,"
Revision 1
- Radiation Work Permit 194482, "Reactor Vessel (RV) Head Disassembly to include, Canopy Seal Clamp (Vendor Activities)," Revision 2
- Radiation Work Permit 194483, "Reactor Vessel (RV) Head Reassembly to include, Canopy Seal Clamp (Vendor Activities)," Revision 1
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Engineering Controls (IP Section 02.01) (1 Sample)
The inspectors evaluated airborne controls and radioactive monitoring.
- (1) The inspectors reviewed the following:
Installed Ventilation Systems
- Fuel building emergency exhaust system
- Containment purge exhaust system
Temporary Ventilation System Setups
- 500 cubic feet per minute high efficiency particulate air unit, Radiation Work Permit 194050
Portable or Installed Monitoring Systems
- Containment 2047 feet
- Containment 2000 feet
Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample)
The inspectors evaluated the licensees use of respiratory protection devices by:
- (1) Observing in-field applications; verifying the licensee validated the level of protection provided by the devices; inspecting the material condition of devices, reviewing records and certification of devices issued for use; reviewing the qualifications of workers that use the devices; and observing workers donning, doffing, and testing devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 02.03) (1 Sample)
The inspectors evaluated self-contained breathing apparatus program implementation.
- (1) The inspectors reviewed the following:
Status and Surveillance Records for Self-Contained Breathing Apparatus
- S/N 115S1543108008
- S/N 115S1543016987
- S/N 115S1543009024
Self-Contained Breathing Apparatus Fit for On-Shift Operators
- On Shift Operators, Tuesday, October 1, 2019, Day Shift
- On Shift Operators, Thursday, October 3, 2019, Day Shift
Self-Contained Breathing Apparatus Maintenance Check
- S/N 115S1543108008
- S/N 115S1543016987
- S/N 115S1543009024
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicator submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12)===
- (1) The inspectors reviewed Drill/Exercise Performance opportunities conducted between April 2018 and September 2019.
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) The inspectors reviewed ERO Drill Participation data for drills and exercises conducted between April 2018 and September 2019.
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) The inspectors reviewed tests of offsite emergency warning sirens conducted between April 2018 and September 2019.
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) October 1, 2018, to September 30, 2019
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) October 1, 2018, to September 30, 2019
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) October 1, 2018, to September 30, 2019
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2018, to September 30, 2019
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, 2018, to September 30, 2019
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the area of safety conscious work environment (SCWE) and assessed the licensee's progress in addressing the SCWE theme.
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) NRC Operating Experience Smart Sample 2018/01, Evaluation of Licensee Actions Taken in Response to 10 CFR Part 21 Notification of the Potential Existence of Defects Related to Control Rod Drive Mechanism Thermal Sleeves
- (2) Fuel identified with foreign material during the refueling outage
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000482/2019-001-00, "Loss of Startup Transformer Results in Emergency Diesel Generator Actuation" (ADAMS Accession: ML19281C061). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred. This licensee event report is closed.
- (2) LER 5000482/2019-002-00, "Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure" (ADAMS Accession: ML19295D729). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred. This licensee event report is closed.
INSPECTION RESULTS
Observation: Semiannual Trend Review 71152 The inspectors reviewed the licensees corrective action program for potential adverse trends in the area of Safety-Conscious Work Environment (SCWE).
The NRC conducted semiannual baseline inspections during this year to assess the corrective actions taken to address the existing SCWE cross-cutting theme. Based on these recent inspections and review of the licensees actions taken and planned in response to the issuance of a violation of 10 CFR 50.7, the NRC determined that a theme in the SCWE area continued to exist; however, recent survey results indicate an improvement in some areas, Engineering And Security, but mixed results in others.
Consistent with NRC guidance, the licensees progress in addressing the SCWE theme will continue to be reviewed on a semiannual basis. During the current inspection, the inspectors review included consideration of previous NRC reviews of the licensees progress in addressing the SCWE theme, recent actions that the licensee has completed or planned to address the cross-cutting theme in the SCWE area, and consideration of recent enforcement actions taken by the NRC.
The inspectors reviewed approximately 38 condition reports that were directly or potentially related to SCWE. The number of condition reports from January 2019 to June 2019 was compared against the number of SCWE condition reports that were written between July 2019 to December 2019. The specific content of the SCWE condition reports was evaluated and the number of anonymous SCWE condition reports was assessed. In addition, the inspectors reviewed and compared results of the licensee's September 2018 SCWE pulse survey and April 2019 site-wide SCWE survey. The inspectors also reviewed a June 2019 peer (STARs) assessment, a Nuclear Safety Culture Assessment conducted in August 2019, and a Level of Effort Evaluation completed in October 2019.
Assessment
With regard to actions taken to address the cross-cutting theme in the SCWE area, it appears that the licensee is applying the corrective actions as described in its improvement plan. Many of the corrective actions taken include senior management presentations to the staff (referred to as "blitzes"), group training for managers, group training for employees, and procedural changes. At the time of this inspection, the licensee had completed nearly three quarters of their planned actions. All the blitzes and planned procedure changes have been completed, and the licensee was expecting to complete all associated training by December 31, 2019. The licensee still had some actions remaining on their plan, including evaluating the effectiveness of the completed actions. The inspectors reviewed the licensees actions and did not identify any significant concerns.
During a previous inspection, the inspectors identified to the licensee that it appeared that the licensee's corrective action plan had a focus on staff level interactions with first line supervision. Specifically, the corrective action plan had a focus on identifying those behaviors in the first line supervision and mid-level management that might contribute to a chilled work environment. The inspectors, based on the cause of the violation in question, asked the licensee if there were any actions planned for senior management with regard to peer review and assessment (i.e., training that focused on mid-level management reporting on senior management behaviors that may contribute to a chilled work environment, or senior manager peer-to-peer reporting). The licensee wrote Condition Report 133982. The licensee indicated in this condition report that the training provided as part of the overall plan should be adequate, but the licensee noted that it would re-evaluate adequacy in 2020 to see if other actions were needed to address this question.
The inspectors reviewed the licensee's survey results and Level of Effort Evaluation, and it was noted that the results were mixed. Some priority groups, such as Security and Engineering, showed some improvement, while other groups, such as Maintenance Support, appeared to remain static. In addition, there were a couple of condition reports that raised concerns that some supervisors had not significantly altered their behaviors or communication styles following the "blitzes."
Regarding the trend of SCWE-related condition reports, the inspectors did note a slight decrease in number. However, with respect to anonymous condition reports, the inspectors noted that the quantity did not appear to decrease, which may indicate that there are still employees who do not feel comfortable bringing their concerns directly to their management. Finally, the licensee has made a change to the documenting process for anonymous condition reports. Specifically, anonymous condition reports cannot be entered electronically anymore, they can only be entered via paper. This resulted in a couple of condition reports critiquing this action.
Observation: Potential Existence of Defects Related to Control Rod Drive Mechanism Thermal Sleeves 71152 The inspectors completed a review of the licensees response to a Westinghouse 10 CFR Part 21 notification (ADAMS Accession No. ML18143B678) regarding the potential existence of defects related to control rod drive mechanism thermal sleeves. The inspection was performed in accordance with NRC Operating Experience Smart Sample (OpESS)2018/01 (ADAMS Accession No. ML18263A261).
The inspectors reviewed evaluation LTR-RIDA-18-223, Evaluation of Thermal Sleeve Flange and OD/ID Wear Conditions and Recommendations, Revision 0, and associated corrective actions taken by the licensee. The inspectors reviewed and verified the adequacy of identified assumptions (i.e., accuracy of measurement technique and applicable wear rates)and the use of plant specific information to identify the most limiting thermal sleeves given the present wear rates. The inspectors also reviewed the results of the licensees thermal sleeve flange wear inspections to verify that the licensee was using the correct thermal sleeve metal wastage in their evaluation. The inspectors verified that the recommended reinspection period of 7.5 effective full power years was aligned with the most limiting locations before reaching their yielding criteria (i.e., ASME Code allowable). Subsequently, the inspectors verified that the licensee had placed the reinspection of control rod drive mechanism thermal sleeves and the evaluation for possible repair or replacement of these components into their corrective action program.
The inspectors concluded that the licensee had used available operating experience and had adequately evaluated for the potential existence of defects in the control rod drive mechanism thermal sleeves. Furthermore, the inspectors verified that applicable corrective actions had been communicated to the appropriate organizations for implementation.
LER (Discussed)
[Atmospheric Relief Valve] and [Main Steam Safety Valve]
Tornado Missile Vulnerabilities Result in Unanalyzed Condition LER 05000482/2017-003-00 71153 Discussion: On September 7, 2017, the licensee identified that there was no retrievable analysis proving that a single tornado driven design basis missile is not capable of affecting more than two atmospheric relief valves. This vulnerability was identified as part of the licensees review of operating experience regarding potential nonconforming conditions related to tornado generated missile effects on main steam safety valves and atmospheric relief valves. These tornado missile vulnerabilities have existed since original plant construction. The licensee invoked Enforcement Guidance Memorandum 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance, Revision 1, implemented initial compensatory measures, and returned the structure, system, and component to an operable-degraded/non-conforming status. NRC Inspection Report 05000482/2017003 (ADAMS Accession No. ML17311B223) dated November 7, 2017, documented that the NRC exercised enforcement discretion by not issuing an enforcement action and allowing continued reactor operation.
At the end of the inspection period, the inspectors had reviewed LER 2017-003-00 and the status of the licensee's corrective actions. The inspectors were unable to close the LER pending licensee action.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 3, 2019, the inspectors presented the IP 71124, Radiation Safety - Public and Occupational cornerstone inspection results to Mr. R. Bayer, Plant Manager, and other members of the licensee staff.
- On October 3, 2019, the inspectors presented the IP 71111.08, Inservice Inspection Activities (PWR), inspection results to Mr. R. Bayer, Plant Manager, and other members of the licensee staff.
- On December 18, 2019, the inspectors presented the 2019 emergency preparedness exercise inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.
- On January 9, 2020, the inspectors presented the integrated inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.
- On January 16, 2020, the inspectors presented the 2019 emergency preparedness exercise inspection results to Mr. M. Dekat, Superintendent Emergency Planning.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SYS EC-121
Cold Weather Operations
7A
Procedures
SYS EF-205
ESW/Circ Water Cold Weather Operations
2A
Procedures
SYS OPS-008
Cold Weather Operations
7A
71111.04Q Corrective Action
Documents
Condition Reports 139565, 139569
71111.04Q Drawings
M-12EC01
Piping & Instrumentation Diagram Fuel Pool Cooling and
Clean-Up System
71111.04Q Drawings
M-12EC02
Piping & Instrumentation Diagram Fuel Pool Cooling and
Clean-Up System
71111.04Q Drawings
M-12EG01
Piping & Instrumentation Diagram Component Cooling
Water System
71111.04Q Drawings
M-12EG02
Piping & Instrumentation Diagram Component Cooling
Water System
71111.04Q Drawings
M-12GT01
Piping & Instrumentation Diagram Containment Purge
Systems HVAC
71111.04Q Miscellaneous
CO: D-OP-S-005
CO Coversheet: Secure System Per Procedure Before
Tagging Drawing Revisions Must Be Verified - GTHZ0007
2/26/2019
71111.04Q Procedures
Control of Locked Component Status
77A
71111.04Q Procedures
CKL EC-120
Fuel Pool Cooling and Cleanup System Normal Valve
Lineup/Breaker Checklist
18A
71111.04Q Procedures
CKL EG-120
Component Cooling Water System Valve, Switch and
Breaker Lineup
71111.04Q Procedures
CKL GT-131
Containment Purge System Elec Checklist
Corrective Action
Documents
Condition Reports 109111, 120554, 121018, 121296, 122457, 123146, 125123,
25273, 127207, 127305, 128264, 128659, 128851, 137260,
137268, 137321, 137369
Drawings
M-189-REK01
Piping and Instrumentation Diagram Residual Heat Removal
System
Procedures
CKL EJ-120
RHR System Lineup
71111.05Q Corrective Action
Documents
Condition Reports 136534, 136540
71111.05Q Miscellaneous
E-1F9905
Fire Hazard Analysis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Procedures
AP 10-106
Fire Preplans
18A
Drawings
10466-A-1319
Architectural Fuel Bldg. Floor Plan El. 2000'-0" & 2026'-0"
Drawings
10466-A-1320
Fuel Building Floor Plan El. 2047'-6" and Roof Plan
Drawings
C-1C1112
Auxiliary Building - Area 1 Concrete Neat Lines Plan - Base
Slab El. 1974' - 0"
Drawings
C-1C1910
Auxiliary Building Conc. Neat Lines & Reinforcing Wall
Elevation - Sheet 10
Drawings
E-1RII22(Q)
Embedded Conduit Auxiliary Building Area -2 El. 1974' - 0"
Drawings
M-12EC01
Piping & Instrumentation Diagram Fuel Pool Cooling System
Drawings
M-12EJ01
Piping and Instrumentation Diagram Residual Heat Removal
System
Drawings
M-12LF05
Piping & Instrumentation Diagram Auxiliary Building Floor &
Equip. Drain System
Drawings
M-13EC05
Piping Isometric Fuel Pool Cooling & Clean-Up Sys. Fuel
Building
Drawings
M-13EC07
Piping Isometric Fuel Pool Cooling & Clean-Up Sys.
Radwaste Building
Drawings
M-1P1121
Embedded Drainage Systems (LF) Auxiliary Building El.
1967' - 0" & 1974' - 0" Area 2
Drawings
M-663-00017
Wolf Creek Nuclear Operating Corporation Penetration Seal
Typical Details
W22
Drawings
M-OT1261
Fuel Bldg/Hot Mach. Shop Trench Piping Plan & Sections
Miscellaneous
APF 05D-001-01
Calculation Sheet: Calculation No. FL-02
Miscellaneous
APF 05D-001-01
Calculation Cover Sheet: Flooding of Fuel Building EL 2000'-
0" Rooms - Calculation No. FL-09
Miscellaneous
M-12LF05
Piping & Instrumentation Diagram Auxiliary Building Floor &
Equip. Drain System
Procedures
STS PE-033
CCW Heat Exchanger Performance Test
Work Orders
18-443630-000
Corrective Action
Documents
Condition Reports 121793, 122185, 122379, 122440, 122447, 122485, 122562,
2710, 122802, 123098,123902, 124064, 124279, 124647,
24966, 126010, 126046, 128153, 128246, 128716, 129065,
29501, 129758, 130114, 130292, 130775, 130851, 130910,
131148, 132260, 133009, 133424
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Wolf Creek Generating Station, Unit 1 - Request for Relief
14R-06 from American Society of Mechanical Engineers
Boiler and Pressure Vessel Code Visual Examination
Requirements for Reactor Vessel Head Penetration Nozzle
Weld Specified by Code Case N-729-4
10/18/2018
Miscellaneous
MF7423
Wolf Creek Generating Station-Request for Relief 14R-01 to
Continue Use of an Alternative Risk-Informed Methodology
in Selecting Class 1 and Class 2 Piping Welds for Inservice
Inspection During the Forth 10-Year Interval
11/30/2016
Miscellaneous
MF7425
Wolf Creek Generating Station-Request for Relief 14R-02
for Alternative to ASME Code Inspection Requirements for
Class 1 Reactor Pressure Vessel Supports
08/23/2016
Miscellaneous
Wolf Creek Generation Station, Unit 1 - Request for Relief
from Requirements of the American Society of Mechanical
Engineers Boiler and Pressure Vessel Code, Code Case
N-666-1
2/12/2018
Miscellaneous
MF8456
Wolf Creek Generating Station-Relief from Certain
American Society of Mechanical Engineers Boiler and
Pressure Vessel Code Inservice Inspection Requirements
for Reactor Vessel Closure Head Penetration Nozzles
During Refueling Outage 21 and the Fourth 10-Year
Inservice Inspection Interval
05/01/2017
Miscellaneous
MF9639
Wolf Creek Generating Station - Request for Relief 14R-05
from Certain Pressure Test Requirements of the American
Society of Mechanical Engineers Boiler and Pressure Vessel
Code for Reactor Pressure Vessel Leak-Off Lines for the
Fourth 10-Year Inservice Inspection Interval
08/02/2017
Miscellaneous
WCRE-30
Inservice Inspection Program Plan, Wolf Creek Generating
Station, Interval 4
2/22/2018
Procedures
AI 16F-001
Evaluation of Boric Acid Leakage
Procedures
AI 16F-002
Boric Acid Leakage Management
Procedures
Boric Acid Corrosion Control Program
Procedures
DC24 07/02/2019
Welding Program Manual
Procedures
LMT-08-PDI-UT-1 Ultrasonic Examination of Ferritic Piping Welds
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
LMT-08-PDI-UT-2 Ultrasonic Examination of Austenitic Piping Welds
Procedures
LMT-08-PDI-UT-3 Ultrasonic Through Wall Sizing in Piping Welds
Procedures
LMT-08-UT-004
Ultrasonic Examination of Vessel Welds and Adjacent Base
Metal > 2.0 in Thickness
Procedures
QCP-20-501
Visible Dye Penetrant Examination
10A
Procedures
QCP-20-502
Magnetic Particle Examination AC/DC Yoke and AC Coil
Techniques
Procedures
QCP-20-503
Ultrasonic Examination for Component Wall Thinning
Procedures
QCP-20-508
Radiographic Examination of Welds
4B
Procedures
QCP-20-541
VT-3 Visual Examination
Procedures
WPD-1
Welding Program Description
Self-Assessments QH-2019-1866
Assessment for NRC RF23 ISI inspection
06/06/2019
Self-Assessments QH-2019-1871
Boric Acid Program Assessment for NRC RF23 ISI
inspection
06/17/2019
Self-Assessments QH-2019-1875
RF23 Readiness for NRC ISI Inspection
06/19/2019
Self-Assessments SA-2018-0140
ISI Pressure Test Self Assessment
01/17/2019
Work Orders
14-387463, 17-422890, 17-422899, 17-426657, 18-438730,
18-438963, 18-439101, 18-439263, 18-440094,
71111.11Q Procedures
AP 21-001
Conduct of Operations
83A
71111.11Q Procedures
GEN 00-002
Cold Shutdown to Hot Standby
103
71111.11Q Procedures
GEN 00-003
Hot Standby to Minimum Load
2
71111.11Q Procedures
RXE 01-002
Reload Low Power Physics Testing
Corrective Action
Documents
Condition Reports 125518, 125777, 126839, 129032, 135326, 136537, 136880,
137321
Miscellaneous
Maintenance Rule Final Scope Evaluation: Shutdown Diesel
Generators - KU-01
10/09/2019
Miscellaneous
Maintenance Rule Final Scope Evaluation: Shutdown Diesel
Generators - KU-02
10/09/2019
Miscellaneous
Maintenance Rule Final Scope Evaluation: Residual Heat
Removal/MSPI Residual Heat Removal System - EJ-01
10/02/2019
Miscellaneous
Maintenance Rule Final Scope Evaluation: Residual Heat
Removal/MSPI Residual Heat Removal System - EJ-02
10/02/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Maintenance Rule Final Scope Evaluation: Residual Heat
Removal/MSPI Residual Heat Removal System - EJ-06
10/02/2019
Miscellaneous
Equipment Performance Evaluation: CR Number - 125518
Miscellaneous
APF 23M-001-01
Maintenance Rule (a)(1) Determination Section I: Station
Blackout Diesel Generation System (KU)
2/19/2018
Miscellaneous
EDI 23M-050
Engineering Desktop Instruction Monitoring Performance to
Criteria and Goals: Function Failure Determination Checklist
- System: KU
11/29/2018
Procedures
AI 28A-100
Condition Report Resolution
Procedures
Miscellaneous
APF 22B-001
Shutdown Safety Function Status & Assessment Summary
2A
Procedures
Outage Risk Management
Work Orders
13-372401-018
Calculations
P-254
Normal Charging Loop 1 Snubber Reduction Analysis -
Reactor Building
005
Corrective Action
Documents
Condition Reports 136012, 136383, 136412, 136553, 136672, 136709, 136749,
136750, 136752, 136790, 136851, 136940, 137333, 137389,
137826, 139619
Drawings
Schematic Input Buffer
2/22/1977
Drawings
SA075A Main Steam (MS) One Line Diagram
W01
Drawings
SA075B Main Steam (MS) One Line Diagram
W01
Drawings
KL1909
Logic Block Diagram Load Shedding & Emergency Load
Sequencing System (LSELS)
09/29/1978
Drawings
M-12AB02
Piping & Instrumentation Diagram Main Steam System
Drawings
M-13HB33
Small Piping Isometric Liquid Radwaste System Radwaste
Building
Drawings
M-151-00004
Nozzle Type Relief Valve
W07
Miscellaneous
Engineering White Paper
2/17/2019
Miscellaneous
Pictures of fuel assemblies: AA17, AA59, AC47, and AC53
Miscellaneous
20322
Design Equivalent Change Package: Encapsulation to Seal
BB8378A Bonnet Boric Acid Leakage
Miscellaneous
9002-DRPI-000
Principles of Operation (Figure 2-30)
Miscellaneous
Boric Acid Evaluation: CVCS Normal Charging to Loop 1
10/08/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
APF 05C-004-01
Basic Engineering Disposition: ESW-B Traveling Screen
High Vibration 19-455350-001
10/15/2019
Miscellaneous
APF 26A-001-01
RER Reportability Determination: RER No. 2019-021
10/22/2019
Miscellaneous
Letter WO 96-
0068
Docket No. 50-482: Response to Generic Letter 96-01,
"Testing of Safety Related Logic Circuits"
04/18/1996
Miscellaneous
TS Bases
Technical Specification Bases
Miscellaneous
TS Bases
Technical Specification Bases
Procedures
Operability Determination and Functionality Assessment
38A
Procedures
EMG E-O
Reactor Trip or Safety Injection
41A
Procedures
STS IC-208A
4KV Loss of Voltage & Degraded Voltage TADOT NB01 Bus
- SEP GRP 1
6B
Procedures
STS IC-208B
4KV Loss of Voltage & Degraded Voltage TADOT NB02 Bus
- SEP GRP 4
Procedures
STS RE-017
DRPI Operability Verification
10B
Work Orders
Work Orders
17-426808-000, 19-454475
Corrective Action
Documents
Condition Reports 114660, 139590
Drawings
M-12GL01
Piping & Instrumentation Diagram Auxiliary Building HVAC
Miscellaneous
APF 29B-003-01
Surveillance Test Routing Sheet: Train B RHR System
Inservice Valve Test
10/17/2019
Procedures
MPE RC-001
Room Cooler Maintenance
Procedures
QCP-20-514
Procedures
STN EG-003B
CCW Train B Void Monitoring & Venting
Procedures
STN PE-037B
ESW Train B Heat Exchanger Flow and DP Trending
Procedures
STS EF-100B
ESW System Inservice Pump B & ESW B Check Valve Test
Procedures
STS EJ-209B
Train B RHR System Inservice Valve Test
Procedures
STS GN-001
CTMT Cooling Fans Operability Test
Procedures
STS KJ-005B
Manual/Auto Start, Sync & Loading of EDG NE02
65A
Procedures
STS KJ-011A
EDG NE01 24 Hour Run
Procedures
STS MT-077
CCW Return to CCW Pumps Check Valve Inspection
Procedures
SYS EF-201
ESW Screen Wash Operation
20A
Procedures
SYS EG-400
Component Cooling Water System Fill and Vent
Procedures
SYS GN-120
Containment Cooling System Operation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SYS KJ-124
Post Maintenance Run of Emergency Diesel Generator B
Work Orders
Work Orders
13-364660, 13-372401, 15-399213-013, 15-402735,
15-406050, 16-418607, 17-432437-014, 18-441543-000,
18-441543-002, 18-442257, 18-442288, 18-442401,
18-443270, 18-443621-001, 18-443732, 18-443783,
19-451230-000
Corrective Action
Documents
Condition Reports 137772, 138117, 138118, 139349
Drawings
C-OC1211
Auxiliary Building Area 1 Concrete Neat Lines Plan Floor
EL. 1988'- 0"
Drawings
C-OC1221
Auxiliary Building Area 2 Concrete Neat Lines Plan Floor
EL. 1988' - 0"
Drawings
M-12BB01
Piping & Instrumentation Diagram Reactor Coolant System
Drawings
M-12BG01
Piping & Instrumentation Diagram Chemical and Volume
Control System
Drawings
M-OX1221
Auxiliary Building Area 2 Penetration Closure Plan Floor
EL. 1988' - 0"
Miscellaneous
APF 15C-002-01
Procedure Cover Sheet: Reload Low Power Physics Testing
- RXE 01-002
Miscellaneous
CO: D-OP-S-005
CO Coversheet: Secure System Per Procedure Before
Tagging Drawing Revisions Must Be Verified - GTHZ0007
2/26/2019
Miscellaneous
CO: R-BG-L-001
CO Coversheet: Secure System Per Procedure Before
Tagging Drawing Revisions Must Be Verified - BGHV8149A
11/01/2019
Miscellaneous
EmpCenter Data
(15 Workers)
Work Hour Reports
09/07/2019
to
11/15/2019
Miscellaneous
M-663-00017
Wolf Creek Nuclear Operating Corporation Penetration Seal
Typical Details
W22
Procedures
AP 13-001
Fatigue Management
20D
Procedures
GEN 00-003
Hot Standby To Minimum Load
103
Procedures
STN KU-001B
SBO DG to NB02 Functional Test
Procedures
STS KJ-001A
Integrated D/G and Safeguards Actuation Test - Train A
Procedures
STS KJ-001B
Integrated D/G and Safeguards Actuation Test - Train B
Procedures
I-ENG-026
Local Leak Rate Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STS EF-001A
ESW System Inservice Pump A & ESW A Check Valve Test
Procedures
STS KJ-001B
Integrated D/G and Safeguards Actuation Test - Train B
Procedures
STS PE-125
LLRT Valve Lineup for Penetration 25
Corrective Action
Documents
Condition Reports 119506,119507, 119869, 119911, 119915, 119941, 120109,
21171, 121173, 121729, 122130, 122348, 125976, 126201,
26213, 126222, 126240, 127643, 127649, 127651, 127665,
28016, 128018, 128019, 129197, 129586, 129774, 130241,
130282, 130286, 130296, 130301, 130306, 130313, 130321,
130440, 130679, 131782, 131802, 131821, 131822, 131851,
131944, 132067, 132249, 132417, 132424, 132430, 132450,
2772, 133765, 134128, 134497, 134924, 134930, 134933,
134946, 134948, 134953, 134964, 134966, 134967, 135038,
138628, 138707, 138723, 139116
Corrective Action
Documents
Resulting from
Inspection
Condition Reports 138995, 139002, 139006, 139008, 139009, 139011, 139012,
139013, 139015, 139016, 139017, 139019, 139020, 139021,
139025, 139026, 139027, 139028, 139037, 139039, 139040,
139045, 139047, 139048, 139050, 139053, 139054, 139063,
139126, 139130
Miscellaneous
TR 2018-215
Training Request
Miscellaneous
Procedure Change Requests PCR 69855, PCR 69858,
PCR69859
Miscellaneous
18-SA-02
Drill Type: Semi-Annual, Drill Requirements: Full Scope, HP,
PPX, Communications Drill, Radiological Monitoring
11/15/2018
Miscellaneous
APF 06-002-02
Emergency Action Levels Technical Bases
0B
Miscellaneous
Radiological Emergency Response Plan, R20
9/11/2019
Miscellaneous
EPF 06-018-11
Technical Support Center Inventory Checklist
Miscellaneous
EPF 06-018-12
Emergency Operations Facility Inventory Checklist
Miscellaneous
Docket No. 50-482: Revision of One Procedure that
Implements the Radiological Emergency Response Plan
(RERP) for Wolf Creek Generating Station (WCGS)
1/30/2019
Miscellaneous
Docket No. 50-482: Revision of Two Forms that Implement
the Radiological Emergency Response Plan (RERP) for Wolf
Creek Generating Station (WCGS)
2/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Docket No. 50-482: Revision of Two Procedures and Four
Forms that Implement the Radiological Emergency
Response Plan (RERP) for Wolf Creek Generating Station
(WCGS)
5/28/2019
Procedures
AI 28A-010
Screening Condition Reports
Procedures
AP 21-001
Conduct of Operations
83A
Procedures
EPP 06-018
Maintenance of Emergency Facilities and Communications
Checks
Procedures
EPP 06-019
Alert and Notification System Sirens
9B
Procedures
EPP-06-001
Control Room Operations, R30A
11/82019
Procedures
EPP-06-002
Technical Support Center Operations, R43
9/11/2019
Procedures
EPP-06-003
Emergency Operations Facility Operations, R27
9/11/2019
Procedures
EPP-06-005
Emergency Classification, R9A
2/14/2019
Procedures
EPP-06-006
Protective Action Recommendations, R10
9/26/2019
Procedures
EPP-06-007
Emergency Notifications, R26
9/26/2018
Procedures
EPP-06-009
Drill and Exercise Requirements, R11A
11/13/2018
Procedures
EPP-06-011
Emergency Team Formation and Control, R12
9/11/2019
Procedures
EPP-06-013
Exposure Control and Personnel Protection, R6A
5/6/2018
Procedures
EPP-06-015
Emergency Response Organization Callout, R14
9/30/2015
Corrective Action
Documents
Condition
Reports-
26669, 129586
Corrective Action
Documents
Resulting from
Inspection
Condition Reports 139133
Miscellaneous
E-Plan Screening - Activity/Document Number: APF 06-002-
2, Revision: 0B
1/10/2019
Miscellaneous
E-Plan Screening - Activity/Document Number: APF 06-002-
03, Revision: 0B
1/14/2019
Miscellaneous
Wolf Creek Generating Station, Unit 1 - Issuance of
Amendment Re: Revision to the Emergency Plan (EPID L-
2018-LLA-0138)
4/1/2019
Miscellaneous
STARS 480
Changes to the Emergency Plan description that do not
reduce the commitments set forth in the previously-approved
7/1/2005
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Docket No. 50-482: License Amendment Request (LAR) for
Revision to the Emergency Plan
5/9/2018
Miscellaneous
Docket No. 50-482: Response to Requests for Additional
Information (RAI) Regarding License Amendment Request
(LAR) for Revision to the Emergency Plan
11/19/2018
Procedures
Communications with the Nuclear Regulatory Commission
Corrective Action
Documents
Condition Reports 119737, 119739, 119754, 119762, 120567, 120680, 120708,
20975, 121099, 121159, 121281, 121282, 121495, 121601,
21726, 122202, 124071, 124104, 122444, 124823, 125181,
25880, 126557, 126571, 126577, 127145, 128132, 129523,
131088
Procedures
Special Nuclear Material Safeguards and Accountability
Procedures
Radiation Worker Guidelines
Procedures
FHP 02-019
Spent Fuel Pool Exclusion Area
Procedures
RPP 02-105
Radiation Work Permit (RWP)
Procedures
RPP 02-210
Radiation Survey Methods
49B
Procedures
RPP 02-215
Posting of Radiological Controlled Areas
34B
Procedures
RPP 02-605
Control and Inventory of Radioactive Sources
Radiation Work
Permits (RWPs)
2300
Crane Operators, Riggers, Iron Workers, Tool Crib Workers,
Fire Watch, Coatings, Housekeeping, and Cleaner Support
Personnel
Radiation Work
Permits (RWPs)
194482
IRV Head Disassembly to include Canopy Seal Clamp
(Vendor Activities)
Radiation Work
Permits (RWPs)
194483
RV Head Reassembly to include Canopy Seal Clamp
(Vendor Activities)
Self-Assessments QS 2019-3094
Quality Assurance Review: Temporary Shielding Request
Packages
10/03/2019
Self-Assessments Quick Hit 2019-
1893
NRC Inspection Procedure 71124.01, Radiological Hazard
Assessment and Exposure Controls
04/17/2019
Corrective Action
Documents
Condition Reports 120334, 120975, 121159, 121281, 121282, 122130, 122348,
24071, 126557, 126577, 127145, 128131, 130911, 135180,
136261, 136365, 136370,
Procedures
AI 14-009
Industrial Respiratory Protection Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AI-10-001
Fire Brigade Equipment Inventory, Maintenance and
Cleaning
Procedures
Radiation Worker Guidelines
Procedures
Respiratory Protection Program at Wolf Creek
Procedures
GT1245302
Self-Contained Breathing Apparatus User
Procedures
RPP 02-105
Procedures
RPP-03-310
Respiratory Protection Equipment
Procedures
SYS GG-201
Fuel Building HVAC System Operation
10A
Procedures
SYS GT-121
Containment Shutdown Purge System Operation
Radiation Work
Permits (RWPs)
180049
Decon Inside High Radiation Areas, High Contamination
Areas, Discrete Radioactive Particle Area, and Alpha Level 2
Areas
Radiation Work
Permits (RWPs)
2300
Crane Operators, Riggers, Iron Workers, Tool Crib Workers,
Fire Watch, Coatings, Housekeeping & Cleaner Support
Personnel
Radiation Work
Permits (RWPs)
194050
SI "B" Pump and Motor Work/Inspection 1974'Aux Room
1108
Radiation Work
Permits (RWPs)
196000
Lower Refueling Cavity Pre and Post Flooding Maintenance
Activities
Self-Assessments Quick Hit Number
2019-1894
NRC Inspection Procedure 71124.03, In-Plant Airborne
Radioactivity Control and Mitigation
71151
Corrective Action
Documents
Condition Reports 126201, 126533, 129679, 132774, 133765, 133805, 133901
71151
Miscellaneous
MSPI Derivation Report - MSPI Residual Heat Removal
System - Unavailability Index
2/11/2019
71151
Miscellaneous
MSPI Derivation Report - MSPI Residual Heat Removal
System - Unreliability Index
2/11/2019
71151
Miscellaneous
MSPI Derivation Report - MSPI Residual Heat Removal
System - Performance Limit Exceeded
2/11/2019
71151
Miscellaneous
MSPI Derivation Report - MSPI Heat Removal System -
Unreliability Index
2/11/2019
71151
Miscellaneous
MSPI Derivation Report - MSPI Heat Removal System -
Unavailability Index
2/11/2019
71151
Miscellaneous
MSPI Derivation Report - MSPI Residual Heat Removal
2/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System - Performance Limit Exceeded
71151
Miscellaneous
LER 2018-001-00
Inappropriate Use of Blind Flange for Containment Isolation
Valve Results in Condition Prohibited by Technical
Specifications
10/04/2018
71151
Miscellaneous
LER 2018-002-00
Modification Activities Affected Control Room Envelope
Boundary Causing a Condition Prohibited by Technical
Specifications
2/27/2019
71151
Miscellaneous
LER 2019-001-00
Loss of Startup Transformer Results in Emergency Diesel
Generator Actuation
07/18/2019
71151
Miscellaneous
STN CH-024
Quarterly/Yearly Dose Projections: April 17, 2018, through
September 19, 2019
71151
Miscellaneous
WCNOC-163
Mitigating System Performance Index (MSPI) Basis
Document
71151
Procedures
AI 26A-008
INPO/NRC/STARS Performance Indicator Guidelines
71151
Procedures
NRC Performance Indicators
71151
Procedures
EPP-06-019
Alert and Notification Siren Systems, R9B
10/18/2018
71151
Procedures
EPP-06-022
Tone Alert Radio Maintenance/Compensatory Measures
11/13/2018
71151
Work Orders
Corrective Action
Documents
Condition Reports 122351, 123083, 123084, 129698, 132017, 132610, 132652,
2744, 133430, 133543, 133907, 133935, 133979, 133982,
134101, 134102, 134103, 134106, 134722, 134889, 134984,
135205, 135873, 135891, 135950, 136226, 136383, 136412,
136640, 136641, 136672, 136683, 136688, 136709, 136744,
136749, 136750, 136752, 136790, 136801, 136802, 136803,
136804, 136805, 136810, 136851, 136924, 137699, 138224,
138754, 139225
Drawings
1464F11
Thermal Sleeve
Drawings
M-703-00055
Closure Head (SAP) General Assembly
W02
Engineering
Evaluations
LTR-RIDA-18-223 Evaluation of Thermal Sleeve Flange and OD/ID Wear
Conditions and Recommendations
Engineering
Evaluations
PWROG-16003-P Evaluation of Potential Thermal Sleeve Flange Wear
Engineering
Evaluations
PWROG-16003-P Evaluation of Potential Thermal Sleeve Flange Wear
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
MRP 2018-010
Notification of Recent PWR CRDM Thermal Sleeve Flange
Wear and Control Rod Motion Stoppage Operating
Experience and Recommended Plant Actions
03/20/2018
Miscellaneous
TB-07-2
Reactor Vessel Head Adapter Thermal Sleeve Wear
Corrective Action
Documents
Condition Reports 13957, 15576, 18497, 20105, 32801, 132693, 134184,
134814
Drawings
908 663
Valve, Thermostatic 3-Way ICW ASME Sect. III, CL 3
05/10/1977
Drawings
908 664
Valve, Thermostatic 3-Way
- J.W. ASME Sect. III, CL 3
05/10/1977
Drawings
908 665
Valve, Thermostatic 3-Way
- L.O. ASME Sect. III, CL 3
05/10/1977
Drawings
N-84984-E2
5" 3-Way Temp. Regulatory ANSI Class 150 Steel
Miscellaneous
APF 24G-001-01
Commercial Grade Dedication Package Number 009-P0002
Miscellaneous
APF 28A-000-01
Performance Improvement Request Initiation:
PIR 2004-2160
08/21/2004
Miscellaneous
APF 28A-001-01
Performance Improvement Request Initiation:
PIR 2004-2160
08/21/2004
Miscellaneous
LER 2019-002-00
Emergency Diesel Generator Inoperable Due to
Temperature Control Valve Failure
10/14/2019
Miscellaneous
Letter NO 92-
0195
Docket No. 50-482: Special Report 92-002
07/08/1992
Miscellaneous
PIR 1999-1886
Miscellaneous
PIR 2000-2462
Miscellaneous
PIR 2004-2160
Miscellaneous
Product
Specification I-
285-P, Q, S, T
Robertshaw Sales Manual Section 351
Miscellaneous
WCNOC-67
Shelf Life Guidelines
Miscellaneous
Docket No. 50-482; Special Report 89-003, WCNOC Letter
NO 90-0009 dated January 8, 1990, from
WCNOC to NRC
2/18/1993
Procedures
ALR 501
Standby Diesel Engine System Control Panel KJ-121
Procedures
Stored Item Maintenance, Shelf Life, Storage Level &
Storage Packaging
Work Orders
00-220529-050, 01-227134-000, 01-230949-002,
19-450841-000, 19-453254-000, 19-453567-002
30