IR 05000482/2022010
| ML22119A162 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/05/2022 |
| From: | Ami Agrawal NRC Region 4 |
| To: | Reasoner C Wolf Creek |
| References | |
| IR 2022010 | |
| Download: ML22119A162 (17) | |
Text
May 05, 2022
SUBJECT:
WOLF CREEK GENERATING STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000482/2022010
Dear Mr. Reasoner:
On April 1, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Wolf Creek Generating Station and discussed the results of this inspection with Mr. Jaime McCoy and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations problem identification and resolution program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for problem identification and resolution programs.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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, Signed by Agrawal, Ami on 05/05/22 Ami N. Agrawal, Team Leader Inspection Programs & Assessment Team 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: 05000482/2022010 Enterprise Identifier: I-2022-010-0002 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: Burlington, KS Inspection Dates: March 14, 2022 to April 01, 2022 Inspectors: C. Bickett, Senior Reactor Inspector F. Ramirez Munoz, Senior Reactor Inspector T. Steadham, Senior Resident Inspector J. Vera, Resident Inspector Approved By: Ami N. Agrawal, Team Leader Inspection Programs & Assessment Team Division of Operating Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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
None.
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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors sampled over 220 condition reports and their associated cause evaluations, if applicable. The inspectors also conducted a five-year review of the residual heat removal system, which included review of failures, maintenance issues, surveillances, corrective and preventive maintenance, reliability, and maintenance rule performance. In addition, the inspectors reviewed 19 findings and violations issued during the biennial period.
Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments. The sample included industry operating experience communications like 10 CFR Part 21 notifications and other vendor correspondence, NRC generic communications, publications from various industry groups, and site evaluations. The sample also included reviews of licensee self-assessments and internal audits.
Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment. The team interviewed 42 individuals, observed interactions between licensee employees and management during routine meetings, interviewed the Employee Concerns Program manager and reviewed employee concerns files.
INSPECTION RESULTS
Assessment 71152B Corrective Action Program Assessment Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees performance in each of the areas of Problem Identification, Problem Prioritization and Evaluation, and Corrective Actions adequately supported nuclear safety.
Effectiveness of Problem Identification: Based on the samples reviewed, the team determined that the licensee's performance in this area adequately supported nuclear safety. Overall, the team found that the licensee was identifying and documenting problems at an appropriately low threshold that supported nuclear safety.
Effectiveness of Prioritization and Evaluation of Issues: Overall, the team found that the licensee was appropriately prioritizing and evaluating issues to support nuclear safety. Of the samples reviewed, the team found that the licensee correctly characterized each condition report as to whether it represented a condition adverse to quality, and then prioritized the evaluation and corrective actions in accordance with program guidance.
The inspectors identified an observation in this area associated with the control of procurement documents. As described in inspection report 05000482/2020003 (ADAMS Ascension Number ML20317A261), on October 30, 2019, the A train Class 1E electrical equipment air conditioner unit, SGK05A, tripped after a restart while performing surveillance testing. This issue resulted in NCV 05000482/2020003-01 for the licensees failure to evaluate and install correctly sized fuses to prevent spurious trips of the safety-related Class 1E air conditioner units. During their review of the licensees evaluation to the NCV, the inspectors first noted that the licensees level of effort evaluation (LEE) used language synonymous with vendor deficiencies in their conclusions but no review for Part 21 applicability was performed. Specifically, the licensee reviewed the design specification associated with these air conditioning units and concluded that because the units complied with the design specification, there was no deviation and, therefore, no Part 21 issue. However, this conclusion was not documented. Further, the inspectors noted that the licensee did not review the procurement documents to evaluate the full scope of technical requirements provided to the vendor to conclude that a deviation did not exist.
After discussing this concern with the licensee, the licensee determined that imprecise language was used when describing the vendors culpability with the eventual air conditioning unit trip. The inspectors reviewed the procurement documents and all technical and quality requirements imposed on the vendor for the purchase of the units and concluded that neither a deviation nor a failure to comply with Part 21 requirements existed. However, the inspectors noted that the LEE was reviewed by several layers of the licensees corrective action program personnel, including the corrective action review board, and were concerned that the language used to describe the vendors culpability in the design, did not prompt an inquiry into potential Part 21 implications. While the inspectors determined that a Part 21 violation did not occur, they also noted that more comprehensive technical requirements could have been provided to the vendor which would have resulted in a more robust design of the air conditioning units. The inspectors noted that the licensee's LEE did not address why the design specifications provided to the vendor were not as comprehensive as they could have been. The inspectors discussed with the licensee their concerns with the technical requirements included in the purchase order as well as the concerns with the failure to question the language used in the LEE. The licensee entered the inspectors concerns into their corrective action program as CR 10013298 to further evaluate the issues and to develop additional corrective actions as required.
Effectiveness of Corrective Actions: Overall, the team concluded that the licensee's corrective actions supported nuclear safety. Specifically, the Wolf Creek Generating Station developed effective corrective actions for the problems evaluated in the corrective action program and generally implemented these corrective actions in a timely manner commensurate with their safety significance. As part of this inspection, the team selected the plants residual heat removal system for a focused review within the corrective action program. For this system, the team performed sample selections of condition reports, looking at the adequacy of the licensee's evaluation process for determining which items are placed in the corrective action process, and the corrective actions taken. The team did not identify any concerns with these systems that were not already being addressed by the station's monitoring and corrective action programs Assessment 71152B Use of Self-Assessment & Audits The team reviewed a sample of Wolf Creek Generating Station's departmental self-assessments and audits to assess whether performance trends were regularly identified and effectively addressed. The team also reviewed audit reports to assess the effectiveness of assessments in specific areas. Overall, the team concluded that the licensee had an adequate departmental self-assessment and audit process.
Assessment 71152B Use of Operating Experience The team reviewed a variety of sources of operating experience including part 21 notifications and other vendor correspondence, NRC generic communications, publications from various industry groups. The team determined that Wolf Creek Generating Station is adequately screening and addressing issues identified through operational experience that apply to the station and that this information is evaluated in a timely manner once it is received.
The team noted two observations in this area. First, the licensee routinely enters Part 21 notifications reported to the NRC into their corrective action program to review for applicability to the site. The inspectors noted that these reports were entered and evaluated even in instances where it was clear that the issue did not apply to the site, such as with a recent notification related to BWR/6 fuel assemblies. The inspectors considered this a positive attribute of the licensee's corrective action program to help ensure that conditions adverse to quality are identified and corrected. Second, the inspectors identified a minor violation of 10CFR21.21.a(1) for the licensee's failure to maintain adequate procedures to evaluate deviations and failures to comply to identify defects and failures to comply associated with substantial safety hazards. However, because the inspectors did not identify any instances where the inadequate procedure caused the failure to perform a required evaluation, the inspectors did not consider this deficiency to have a demonstrable negative impact on the licensee's overall Part 21 program.
Assessment 71152B Safety Conscious Work Environment (SCWE)
The team conducted safety conscious work environment interviews with 42 employees from four different disciplines that included maintenance, engineering, operations, and security. The purpose of these interviews was
- (1) to evaluate the willingness of the licensee staff to raise nuclear safety issues, either by initiating a condition report or by another method,
- (2) to evaluate the perceived effectiveness of the corrective action program at resolving identified problems, and
- (3) to evaluate the licensee's safety conscious work environment (SCWE). The team also observed interactions between employees during routine screening review team meetings, daily operational focus meetings, senior leadership review team meetings, and corrective action review board (CARB) meetings. The team interviewed the Employee Concerns Program Manager and reviewed the results of the latest safety culture surveys and a sample of case files that may relate to safety conscious work environment.
The team found that the licensee had a safety conscious work environment where individuals felt free to raise concerns without fear of retaliation. Most expressed positive experiences after raising issues to their supervisors and after documenting issues in condition reports, and all individuals indicated that they would not hesitate to raise safety concerns, through at least one of the several means available at the station. Based on feedback from these interviews regarding anonymous condition reports, the station should consider enhancing communications with plant personnel so that it is better understood how anonymous condition reports are generated.
Minor Violation 71152B Minor Violation: The inspectors reviewed procedure AP 26A-001, Reportable Events -
Evaluation and Documentation, Revision 24 which provided the requirements for Part 21 evaluations and reporting. Attachment D, Step D.2 stated, "The only case where a defect in a basic component of an operating reactor might be reportable under Part 21, but not under 10 CFR 50.72, 50.73, 72.75 or 73.71 would involve safety-related equipment that has been received by WCNOC but is not installed in the plant. The inspectors determined that this step was incorrect and could lead to the failure to report a Part 21 issue because there are instances where an issue may be reportable under Part 21 but not any of the other reporting requirements discussed. Title 10CFR21.21(a)(1) requires, in part, that the licensee shall adopt appropriate procedures to evaluate deviations and failures to comply to identify defects and failures to comply associated with substantial safety hazards. Contrary to the above, the licensee failed to adopt appropriate procedures to evaluate deviations and failures to comply to identify defects and failures to comply associated with substantial safety hazards. Specifically, procedure AP 26A-001 could have incorrectly screened out reportable defects and failures to comply as reportable.
Screening: The inspectors determined the performance deficiency was minor. Specifically, the inspectors did not identify any instances where the failure to adopt appropriate procedures led to the failure to make a required Part 21 notification.
Enforcement:
This failure to comply with 10CFR21.21(a)(1) constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 1, 2022, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Jaime McCoy and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Calculations AN-18-006 Development of alternative source term input parameters 0
71152B Corrective Action CR-xxxxxx or CR 114059, 115120, 115392, 122879, 128909, 129150, 131147,
Documents -100xxxxx 132000, 134185, 136709, 136749, 137521, 138017, 138036,
138042, 138420, 139094, 140012, 140045, 140210, 140802,
141414, 141748, 141881, 141893, 142119, 142189, 143267,
143388, 143412, 143447, 143450, 143599, 143600, 143602,
143607, 143775, 143808, 143975, 144171, 144214, 144260,
144332, 144334, 144348, 144423, 144472, 144595, 144632,
144665, 144752, 144775, 144827, 144895, 145231, 145234,
145267, 145363, 145485, 145499, 145500, 145579, 145714,
145824, 145953, 146165, 146284, 146321, 146344,
1011216, 10000308, 10000457, 10000496, 10000509,
10000584, 10000613, 10000624, 10000626, 10000687,
10000718, 10000781, 10000782, 10000801, 10000824,
10000838, 10000870, 10000891, 10000899, 10000916,
10000922, 10001022, 10001023, 10001045, 10001060,
10001190, 10001612, 10001654, 10001730, 10001777,
10001867, 10001895, 10002101, 10002111, 10002261,
10002673, 10002727, 10002932, 10002997, 10003018,
10003119, 10003596, 10003619, 10003640, 10003703,
10003704, 10003814, 10003913, 10004000, 10004008,
10004252, 10004271, 10004537, 10004589, 10004622,
10004947, 10005362, 10005437, 10005580, 10005622,
10005729, 10005736, 10005789, 10006021, 10006135,
10006141, 10006689, 10007071, 10007096, 10007127,
10007336, 10007337, 10007338, 10007438, 10007672,
10007968, 10008145, 10008272, 10008275, 10008276,
10008277, 10008279, 10008280, 10008282, 10008283,
10008289, 10008456, 10008813, 10008894, 10009145,
10009210, 10009585, 10009587, 10009593, 10009733,
10009801, 10009836, 10010040, 10010238, 10010321,
10010613, 10010895, 10010897, 10010917, 10011036,
Inspection Type Designation Description or Title Revision or
Procedure Date
10011059, 10011216, 10011313, 10011541, 10011637,
10011638, 10012377, 10012565, 10012906, 10012929,
10013134
71152B Corrective Action CR-xxxxxxxx 10013134, 10013298, 10013362, 10013368, 10013370,
Documents 10013371, 10013372, 11013373, 10013374, 10013375,
Resulting from 10013376
Inspection
71152B Drawings M-724-00254, Sh. Model D-100-160 Actuator 16"X12"X16" Class 900 Valve W25
Assembly
71152B Drawings M-724-00758, Sh. Model D-100-160 Actuator 4" Class 900 Valve Assembly 12
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG A Main and 1
SAP-10-3, sh. Bypass Valve DMD Logic
27
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG A Main and 1
SAP-10-3, sh. Bypass Valve DMD Logic
28
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG B Main and 1
SAP-10-3, sh. Bypass Valve DMD Logic
347
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG B Main and 1
SAP-10-3, sh. Bypass Valve DMD Logic
348
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG C Main and 1
SAP-13-3, sh. Bypass Valve DMD Logic
27
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG C Main and 1
SAP-13-3, sh. Bypass Valve DMD Logic
28
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG D Main and 1
SAP-13-3, sh. Bypass Valve DMD Logic
347
71152B Drawings WNA-CB-00320- Wolf Creek Nuclear Operating Company SG D Main and 1
SAP-13-3, sh. Bypass Valve DMD Logic
Inspection Type Designation Description or Title Revision or
Procedure Date
348
71152B Engineering 20350 SGK05A/B Fuse Replacement 0
Changes
71152B Engineering 20406 Copper Sensing Line Replacement 3
Changes
71152B Engineering 20564 Hydrotest for RBB01 Conoseal Clamps 0
Changes
71152B Engineering 9879 Replace SGK04A/B and SGK05A/B Air Conditioning Units 31
Changes
71152B Engineering AN-18-006-000- Development of alternative source term input parameters 0
Changes CN001
71152B Miscellaneous Leadership development program backbone schedule 2020 09/09/2020
though 2028
71152B Miscellaneous Corrective Action Review Board Meeting Minutes 10/15/2020
71152B Miscellaneous Leadership safety culture program lesson plan and
attendance sheet, June 2021
71152B Miscellaneous Executive Safety culture attendance sheet and lesson plan,
December 2018
71152B Miscellaneous Executive Safety culture attendance sheet and lesson plan,
December 2019
71152B Miscellaneous Executive Safety culture attendance sheet and lesson plan,
November 2020
71152B Miscellaneous Executive Safety culture attendance sheet and lesson plan,
October 2021
71152B Miscellaneous Maintenance Rule Final Scope Evaluation
71152B Miscellaneous Maintenance Rule Expert Panel Meeting Agenda 07/11/2018
71152B Miscellaneous Maintenance Rule Expert Panel Meeting Minutes 07/11/2018
71152B Miscellaneous NSRB Report June 2020
71152B Miscellaneous NSRB Report November
21
71152B Miscellaneous PM File 49661
71152B Miscellaneous Corrective Action Review Board Meeting Minutes 08/26/2020
71152B Miscellaneous STARS Indicators Report for 1Q2021 03/31/2021
71152B Miscellaneous STARS Indicators Report for 2Q2021 06/30/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Miscellaneous STARS Indicators Report for 3Q2020 09/30/2020
71152B Miscellaneous STARS Indicators Report for 3Q2021 09/30/2021
71152B Miscellaneous STARS Indicators Report for 4Q2020 12/31/2020
71152B Miscellaneous STARS Indicators Report for 4Q2021 12/31/2021
71152B Miscellaneous Employee Concerns Program Case Logs 03/22/2022
71152B Miscellaneous CAP Backlog Charts 03/16/2022
71152B Miscellaneous Human Performance Flash Update 01/15/2021
71152B Miscellaneous 02-21 Weekly 02-21 Weekly CAP Report 02/21/2022
CAP Report
71152B Miscellaneous 08-0000065642 Purchase order 743118 receipt inspection 12/18/2008
71152B Miscellaneous 10000870 Trend Analysis for Security Human Performance Incidents 01/25/2021
71152B Miscellaneous 10005736 Root Cause Analysis 10005736, Reactor Trip Rev. 0
71152B Miscellaneous 11 November Corrective Action Performance Monitoring Metrics 01/11/2020
CAP Performance November 2020
Indicators
71152B Miscellaneous 11-0000080463 Purchase order 754194 receipt inspection 03/30/2011
71152B Miscellaneous 12/27/2021 12/27/2021 Weekly Extensions Report 12/27/2021
Weekly
Extensions
Report
71152B Miscellaneous 14-0000106551 Purchase order 770164 receipt inspection 10/23/2014
71152B Miscellaneous 144171 Equipment Performance Evaluation - SGK05B Found With Rev. 0
Potential Misaligned Dampers
71152B Miscellaneous 144243 Equipment Performance Evaluation - SGBD Isolation Rev. 0
71152B Miscellaneous 145485 Equipment Performance Evaluation - EFHV0046 Not Rev. 0
Opening
71152B Miscellaneous 146284 Nuclear Safety Culture Work Processes Trait Inputs Trend 01/27/2021
Analysis
71152B Miscellaneous 2021 CAP 12-20-2021 CAP Backlog Charts 12/20/2021
Backlog
71152B Miscellaneous 21-1249 Document revision request to STS PE-040A for CR 16
10002673
71152B Miscellaneous 717200 Purchase order for SGK04A/B and SGK05A/B 14
71152B Miscellaneous 743118 Purchase order for repair of valve components 0
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Miscellaneous 754194 Purchase order for repair and fabrication of valve 1
components
71152B Miscellaneous 770164 Purchase order for repair of valve components 0
71152B Miscellaneous Audit Report No. Quality Assurance Audit Report Security/Cyber Security 03/17/2021
21-01-SC/CS
71152B Miscellaneous ES1311801 Lesson Plan IER L1-14-20 Integrated Risk - Healthy Rev. 001A
Technical Conscience
71152B Miscellaneous M-622.1A Design Specification for Replacement Packaged Air 5
Conditioning Units
71152B Miscellaneous Nov 2020 CAP Nov 2020 CAP Health Index 01/11/2020
Health Index
71152B Miscellaneous NRC Information FLEX Diesel Generator Operational Challenges
Notice 2020-02
71152B Miscellaneous NRC Information Operating Experience Related To Failure Of Buried Fire
Notice 2020-04 Protection Main Yard Piping
71152B Miscellaneous OBSR 2021-2568 Standards - Division Roll-up Scorecard 06/21/2021
71152B Miscellaneous Trend Analysis of Trend Analysis of Past Two Years Of Exam Security Issues 08/30/2021
Past Two Years
Of Exam Security
Issues
71152B Miscellaneous WOL-47402 Failure Analysis: Compressor 2/4/2022
71152B Procedures
71152B Procedures AI 13C-003 Personnel Action Review Board 9
71152B Procedures AI 20E-004 Processing and Maintaining Incoming Operating Experience 1
71152B Procedures AI 22C-010 Operations Work Controls 24A
71152B Procedures AI 23-010 Single Point Vulnerabilities 6A
71152B Procedures AI 23N-001 Air Operated Valve Categorization 5
71152B Procedures AI 23O-001 Functional Importance Determination 7A
71152B Procedures AI 28A-017 Effectiveness Follow-Up 6
71152B Procedures AI 28A-100 Condition Report Resolution 22A
71152B Procedures AI 28A-102 Root Cause Analysis 3A
71152B Procedures AP 15C-002 Procedure Use and Adherence 46E
71152B Procedures AP 18A-001 Employee Concerns Program Revision 9A
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Procedures AP 20A-003 QA Audit Requirements, Frequencies, and Scheduling 35
71152B Procedures AP 20A-004 Conduct of Internal Audits 25
71152B Procedures AP 20A-008 QA Surveillance And Station Monitoring Program Rev. 20
71152B Procedures AP 20B-001 Plant Safety Review Committee 20A
71152B Procedures AP 20E-001 Operating Reactor Experience Program 31A
71152B Procedures AP 23-006 Strategic Engineering Program 28A
71152B Procedures AP 26A-001 Reportable Events - Evaluation and Documentation 21
71152B Procedures AP 26A-001 Reportable Events - Evaluation and Documentation 22
71152B Procedures AP 26A-001 Reportable Events - Evaluation and Documentation 24
71152B Procedures AP 36-001 Nuclear Safety Culture Revision 7
71152B Procedures CKL KJ-121 Diesel Generator NE01 and NE02 Valve Checklist Performed 10/02/2021
on 10/2/2021
71152B Procedures MEC-046 Maintenance Core Work Instructions - 18" Containment 0a
Isolation Purge Valves
71152B Procedures MEC-047 Maintenance Core Work Instructions - 36" Containment 0a
Isolation Purge Valves
71152B Procedures MEC-048 Maintenance Core Work Instructions - 6" Hydrogen Purge 0a
71152B Procedures OFN SB-008 Instrument Malfunctions 53
71152B Procedures STS BG-203B Train B CVCS Excess Letdown Valve Inservice Valve Test Rev. 6
71152B Procedures STS EJ-209A Train A RHR System Inservice Valve Test 01/13/2022
71152B Procedures STS EJ-209B Train B RHR System Inservice Valve Test 01/02/2022
71152B Procedures STS MT-070 ASME Code Testing of Safety/Relief Valves 28
71152B Procedures STS PE-040A Reactor Coolant System Pressure Test 16
71152B Procedures WCNOC OP-01- Leadership Development Program 2
71152B Procedures WCOP-2 Wolf Creek Generating Station Inservice Testing Program for 16
Pumps, Valves, and Snubbers
71152B Procedures WCQPM Wolf Creek Quality Program Manual 13
71152B Procedures WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 12
71152B Self-Assessments 20-04-OPS Quality Assurance Audit (Operations) 05/12/2020
71152B Self-Assessments 20-07-MS Quality Assurance Audit Report - Purchased Material, 08/19/2020
Equipment, and Services
Inspection Type Designation Description or Title Revision or
Procedure Date
71152B Self-Assessments 21-04-MNT/MTE Quality Assurance Audit Report - Maintenance/Measuring 08/26/2021
and Test Equipment
71152B Self-Assessments 22-02-CAP QA Audit Report - Corrective Action Program 03/21/2022
71152B Self-Assessments QA-2021-0558 QA Review of CR 141095 (Anonymous CRs did not all 1/19/2021
receive independent review) generated during the 2020 QA
Audit
71152B Self-Assessments SA-2020-0160 Nuclear safety culture program self-assessment 10/20/2020
71152B Self-Assessments SA-2021-0166 2021 - Nuclear Safety Culture Assessment (NSCA) of Station 01/31/2022
Personnel
71152B Work Orders WO 17-422810-007, 17-422811-007, 17-422810-009, 18-436323-
004, 20-461644-000, 20-462020-003, 19-455368-000, 15-
399867, 20-466687-000, 20-457742-000, 21-474330-000,
11-337546-004, 11-337547-000, 11-337547-002, 11-337547-
003, 11-337548-003, 11-337549-003, 20-461849-003, 20-
2446-000, 20-465698-003, 20-467284-001, 20-467329-
000, 21-470889-000, 21-473455-002, 21-473455-010, 21-
473455-016
14