IR 05000482/2022010

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Biennial Problem Identification and Resolution Inspection Report 05000482/2022010
ML22119A162
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
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:

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

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

AP 15C-002

Procedure Use and Adherence

46E

71152B

Procedures

AP 18A-001

Employee Concerns Program

Revision 9A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Procedures

AP 20A-003

QA Audit Requirements, Frequencies, and Scheduling

71152B

Procedures

AP 20A-004

Conduct of Internal Audits

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

71152B

Procedures

AP 26A-001

Reportable Events - Evaluation and Documentation

71152B

Procedures

AP 26A-001

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

CTMT ISO

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

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