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, 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:
Report Number:
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
71152B
Calculations
AN-18-006
Development of alternative source term input parameters
71152B
Corrective Action
Documents
CR-xxxxxx or CR
-100xxxxx
114059, 115120, 115392, 122879, 128909, 129150, 131147,
2000, 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
Procedure
Type
Designation
Description or Title
Revision or
Date
10011059, 10011216, 10011313, 10011541, 10011637,
10011638, 10012377, 10012565, 10012906, 10012929,
10013134
71152B
Corrective Action
Documents
Resulting from
Inspection
CR-xxxxxxxx
10013134, 10013298, 10013362, 10013368, 10013370,
10013371, 10013372, 11013373, 10013374, 10013375,
10013376
71152B
Drawings
M-724-00254, Sh.
Model D-100-160 Actuator 16"X12"X16" Class 900 Valve
Assembly
W25
71152B
Drawings
M-724-00758, Sh.
Model D-100-160 Actuator 4" Class 900 Valve Assembly
71152B
Drawings
WNA-CB-00320-
SAP-10-3, sh.
27
Wolf Creek Nuclear Operating Company SG A Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-10-3, sh.
28
Wolf Creek Nuclear Operating Company SG A Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-10-3, sh.
347
Wolf Creek Nuclear Operating Company SG B Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-10-3, sh.
348
Wolf Creek Nuclear Operating Company SG B Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-13-3, sh.
27
Wolf Creek Nuclear Operating Company SG C Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-13-3, sh.
28
Wolf Creek Nuclear Operating Company SG C Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-13-3, sh.
347
Wolf Creek Nuclear Operating Company SG D Main and
Bypass Valve DMD Logic
71152B
Drawings
WNA-CB-00320-
SAP-13-3, sh.
Wolf Creek Nuclear Operating Company SG D Main and
Bypass Valve DMD Logic
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
348
71152B
Engineering
Changes
20350
SGK05A/B Fuse Replacement
71152B
Engineering
Changes
20406
Copper Sensing Line Replacement
71152B
Engineering
Changes
20564
Hydrotest for RBB01 Conoseal Clamps
71152B
Engineering
Changes
9879
Replace SGK04A/B and SGK05A/B Air Conditioning Units
71152B
Engineering
Changes
AN-18-006-000-
CN001
Development of alternative source term input parameters
71152B
Miscellaneous
Leadership development program backbone schedule 2020
though 2028
09/09/2020
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
Procedure
Type
Designation
Description or Title
Revision or
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
2/31/2020
71152B
Miscellaneous
STARS Indicators Report for 4Q2021
2/31/2021
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
2-21 Weekly
CAP Report
2-21 Weekly CAP Report
2/21/2022
71152B
Miscellaneous
08-0000065642
Purchase order 743118 receipt inspection
2/18/2008
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
November
CAP Performance
Indicators
Corrective Action Performance Monitoring Metrics
November 2020
01/11/2020
71152B
Miscellaneous
11-0000080463
Purchase order 754194 receipt inspection
03/30/2011
71152B
Miscellaneous
2/27/2021
Weekly
Extensions
Report
2/27/2021 Weekly Extensions Report
2/27/2021
71152B
Miscellaneous
14-0000106551
Purchase order 770164 receipt inspection
10/23/2014
71152B
Miscellaneous
144171
Equipment Performance Evaluation - SGK05B Found With
Potential Misaligned Dampers
Rev. 0
71152B
Miscellaneous
144243
Equipment Performance Evaluation - SGBD Isolation
Rev. 0
71152B
Miscellaneous
145485
Equipment Performance Evaluation - EFHV0046 Not
Opening
Rev. 0
71152B
Miscellaneous
146284
Nuclear Safety Culture Work Processes Trait Inputs Trend
Analysis
01/27/2021
71152B
Miscellaneous
21 CAP
Backlog
2-20-2021 CAP Backlog Charts
2/20/2021
71152B
Miscellaneous
21-1249
Document revision request to STS PE-040A for CR
10002673
71152B
Miscellaneous
717200
Purchase order for SGK04A/B and SGK05A/B
71152B
Miscellaneous
743118
Purchase order for repair of valve components
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152B
Miscellaneous
754194
Purchase order for repair and fabrication of valve
components
71152B
Miscellaneous
770164
Purchase order for repair of valve components
71152B
Miscellaneous
Audit Report No.
21-01-SC/CS
Quality Assurance Audit Report Security/Cyber Security
03/17/2021
71152B
Miscellaneous
ES1311801
Lesson Plan IER L1-14-20 Integrated Risk - Healthy
Technical Conscience
Rev. 001A
71152B
Miscellaneous
M-622.1A
Design Specification for Replacement Packaged Air
Conditioning Units
71152B
Miscellaneous
Nov 2020 CAP
Health Index
Nov 2020 CAP Health Index
01/11/2020
71152B
Miscellaneous
NRC Information Notice 2020-02
FLEX Diesel Generator Operational Challenges
71152B
Miscellaneous
NRC Information Notice 2020-04
Operating Experience Related To Failure Of Buried Fire
Protection Main Yard Piping
71152B
Miscellaneous
OBSR 2021-2568
Standards - Division Roll-up Scorecard
06/21/2021
71152B
Miscellaneous
Trend Analysis of
Past Two Years
Of Exam Security
Issues
Trend Analysis of Past Two Years Of Exam Security Issues
08/30/2021
71152B
Miscellaneous
WOL-47402
Failure Analysis: Compressor
2/4/2022
71152B
Procedures
71152B
Procedures
AI 13C-003
Personnel Action Review Board
71152B
Procedures
AI 20E-004
Processing and Maintaining Incoming Operating Experience
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
71152B
Procedures
AI 23O-001
Functional Importance Determination
7A
71152B
Procedures
AI 28A-017
Effectiveness Follow-Up
71152B
Procedures
AI 28A-100
Condition Report Resolution
2A
71152B
Procedures
AI 28A-102
Root Cause Analysis
3A
71152B
Procedures
Procedure Use and Adherence
46E
71152B
Procedures
Employee Concerns Program
Revision 9A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152B
Procedures
QA Audit Requirements, Frequencies, and Scheduling
71152B
Procedures
Conduct of Internal Audits
71152B
Procedures
QA Surveillance And Station Monitoring Program
Rev. 20
71152B
Procedures
Plant Safety Review Committee
20A
71152B
Procedures
Operating Reactor Experience Program
31A
71152B
Procedures
AP 23-006
Strategic Engineering Program
28A
71152B
Procedures
Reportable Events - Evaluation and Documentation
71152B
Procedures
Reportable Events - Evaluation and Documentation
71152B
Procedures
Reportable Events - Evaluation and Documentation
71152B
Procedures
AP 36-001
Nuclear Safety Culture
Revision 7
71152B
Procedures
CKL KJ-121
Diesel Generator NE01 and NE02 Valve Checklist Performed
on 10/2/2021
10/02/2021
71152B
Procedures
MEC-046
Maintenance Core Work Instructions - 18" Containment
Isolation Purge Valves
0a
71152B
Procedures
MEC-047
Maintenance Core Work Instructions - 36" Containment
Isolation Purge Valves
0a
71152B
Procedures
MEC-048
Maintenance Core Work Instructions - 6" Hydrogen Purge
0a
71152B
Procedures
OFN SB-008
Instrument Malfunctions
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
71152B
Procedures
STS PE-040A
Reactor Coolant System Pressure Test
71152B
Procedures
WCNOC OP-01-
Leadership Development Program
71152B
Procedures
WCOP-2
Wolf Creek Generating Station Inservice Testing Program for
Pumps, Valves, and Snubbers
71152B
Procedures
WCQPM
Wolf Creek Quality Program Manual
71152B
Procedures
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
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,
Equipment, and Services
08/19/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152B
Self-Assessments 21-04-MNT/MTE
Quality Assurance Audit Report - Maintenance/Measuring
and Test Equipment
08/26/2021
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
receive independent review) generated during the 2020 QA
Audit
1/19/2021
71152B
Self-Assessments SA-2020-0160
Nuclear safety culture program self-assessment
10/20/2020
71152B
Self-Assessments SA-2021-0166
21 - Nuclear Safety Culture Assessment (NSCA) of Station
Personnel
01/31/2022
71152B
Work Orders
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