IR 05000482/2024001

Integrated Inspection Report 05000482/2024001

ML24107A888
Person / Time
Site:	Wolf Creek
Issue date:	04/17/2024
From:	Greg Werner NRC/RGN-IV/DORS/PBB
To:	Reasoner C Wolf Creek
References
IR 2024001
Download: ML24107A888 (33)

Text

April 17, 2024

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2024001

Dear Cleve Reasoner:

On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On April 4, 2024, the NRC inspectors discussed the results of this inspection with R. Bayer, General Manager, Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

Two findings of very low safety significance (Green) are documented in this report. Both of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Wolf Creek Generating Station.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Wolf Creek Generating Station.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Signed by Werner, Gregory on 04/17/24

Gregory E. Werner, Chief Reactor Projects Branch B Division of Operating Reactor Safety

Docket No. 05000482 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket Number: 05000482

License Number: NPF-42

Report Number: 05000482/2024001

Licensee: Wolf Creek Nuclear Operating Corp.

Facility: Wolf Creek Generating Station

Location: Burlington, KS

Inspection Dates: January 1 to March 31, 2024

Inspectors: C. Henderson, Senior Resident Inspector R. Kopriva, Senior Project Engineer J. Melfi, Project Engineer D. Proulx, Senior Project Engineer

Approved By: Gregory E. Werner, Chief Reactor Projects Branch B Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Wolf Creek Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Failure to Maintain Surveillance Testing Procedure in Accordance with the Fire Protection Program Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.24 Systems NCV 05000482/2024001-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to maintain a fire protection program procedure.

Specifically, the licensee failed to maintain procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, to perform the required 18-month post-fire safe shutdown normal/bypass (isolation) switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.

Failure to Perform Post-Maintenance Testing Following Maintenance and Installation of the Bypass Reactor Trip Breaker Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.5] - Work 71111.24 Systems NCV 05000482/2024001-02 Management Open/Closed The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.a for the licensee failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability.

Additional Tracking Items

None.

PLANT STATUS

Wolf Creek Generating Station began the inspection period at full power. On March 24, 2024, the unit commenced power coast down. On March 28, 2024, the unit was shut down to begin refueling outage (RF)

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) winter weather advisory with wind gusts of approximately 45 mph and extreme cold weather temperatures on January 16, 2024

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) operator action to isolate a faulted steam generator on February 8, 2024

(2) reactor protection system and anticipated transient without scram actions on February 15, 2024

(3) turbine-driven auxiliary feedwater pump and motor-driven auxiliary feedwater pump A to steam generator D on February 28, 2024

(4) train B class 1E recirculation system for planned maintenance of train A class 1E air conditioning system on March 12, 2024

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the 480 volt AC distribution system on March 14, 2024.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) missed 18-month fire protection surveillance for the isolation/bypass switch for train B essential service water from component cooling water heat exchanger isolation valve, fire area C-27, on January 16, 2024

(2) diesel-driven fire pump area, fire area circulating water screen house, on January 31, 2024

(3) auxiliary building, 2026-foot elevation, fire area A-16, on February 2, 2024

(4) auxiliary feedwater valve compartment number one, fire area A-29, on February 9, 2024

(5) auxiliary panel shutdown room, fire area A-28, on February 14, 2024

(6) reactor protection system motor generator set room, fire area A-27, on February 28, 2024

Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill turbine building north 2032-foot elevation, 480 volt motor control center PG-015 on February 14, 2024.

(2) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill auxiliary building elevation 2026-foot, south electrical penetration room 480 volt load center XPG22 on March 8, 2024.

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal flooding mitigation protections for a feedwater line break inside containment, main steam enclosure, and turbine building on February 15, 2024.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during end of core life moderator temperature coefficient measurement and plant shut down for RF 26 on March 28, 2024.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated just-in-time training for plant shutdown for RF 26 on March 18, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) 480 volt distribution system maintenance and testing on February 21, 2024

(2) reactor protection system and anticipated transient without scram actions maintenance and testing on February 28, 2024

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) class 1E motor-operated valve thermal overload maintenance and testing on March 4, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (9 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) train A safety injection equipment outage January 11, 2024

(2) emergency diesel generator B and train B essential service water equipment outage on January 23, 2024

(3) train B motor-driven feedwater equipment outage on January 29, 2024

(4) circulating water bay C diving activities and unavailability for the diesel and motor-driven fire protection pumps on January 31, 2024

(5) train A essential service water system equipment outage and emergency diesel generator A in maintenance lockout on February 6, 2024

(6) emergency work activities of unplanned nitrogen and instrument air leak for steam generator A atmospheric relief valve and turbine-driven auxiliary feedwater flow control valve accumulator on March 10, 2024

(7) train A class 1E air conditioning system and residual heat removal equipment outage on March 13, 2024

(8) emergent work activities for troubleshooting of a step change in nitrogen leakage for the steam generator D atmospheric relief valve and turbine-driven auxiliary feedwater flow control valve accumulator on March 14, 2024

(9) emergent work activities for emergency diesel generator B failure to manual start on March 29, 2024.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) chemical and volume control valve to safety injection pump A valve, EMHV8924, closed with safety injection pump A unavailable and 100 percent emergency core cooling system flow equivalent from both trains operability determination on January 17, 2024

(2) train B class 1E air conditioning system, SGK05B, tripped on high pressure discharge past operability determination on January 22, 2024

(3) feedwater line D flow accelerated corrosion design pressure requirement operability determination on February 6, 2024

(4) failure to isolate a faulted steam generator with a single failure of the remotely operated valve operability determination on February 27, 2024

(5) emergency diesel generator B governor control load decrease while increasing load during surveillance testing operability determination on February 27, 2024

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) large break loss of coolant accident dose analysis re-evaluation on February 6, 2024

(2) steam generator A atmospheric relief valve gauge block removal on March 13, 2024

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1) (Partial)

The inspectors evaluated RF 26 activities from March 28 - 31, 2024. The inspectors completed inspection procedure sections 03.01.a and 03.01.b.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)

(1) containment cooler D 480 volt breaker fast and slow speed mechanical interlock replacement post-maintenance testing on January 3, 2024

(2) train A containment spray system room cooler belt replacement on January 25, 2024

(3) train A swing inverter, NN15, post-maintenance testing on January 25, 2024

(4) train B essential service water travelling screen post-maintenance testing on January 25, 2024

(5) emergency diesel generator B post-maintenance testing on February 20, 2024

(6) turbine-driven auxiliary feedwater equipment outage post-maintenance testing on February 21, 2024

(7) train B essential service water travel screen motor-operated valve, EFHV0092, corrective and preventative maintenance post-maintenance testing on February 29, 2024

(8) emergent repairs for steam generator A atmospheric relief valve on March 13, 2024

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) train B essential service water motor-operated valve fire protection isolation switch surveillance testing on January 5, 2024

(2) inservice testing requirements for auxiliary feedwater discharge isolation valves ALV032, ALV047, ALV044, ALV035, ALV056, ALV066, ALV071, and ALV061 on February 9, 2024

(3) reactor trip and bypass breaker response time testing and maintenance on February 27, 2024

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) turbine-driven auxiliary feedwater discharge to steam generator air operated valve, ALHV0006, on February 27, 2024

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) simulated reactor coolant pump A shaft shear and failure of automatic reactor trip and manual trip from the control room on January 31,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===

(1) January 1, 2023, through December 31, 2023

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)

(1) January 1, 2023, through December 31, 2023

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) January 1, 2023, through December 31, 2023

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) failure to perform essential service water motor-operated valve 18-month isolation/bypass surveillance extent of condition

(2) failure to perform adequate reactor trip breaker work planning, and post-maintenance testing

INSPECTION RESULTS

Failure to Maintain Surveillance Testing Procedure in Accordance with the Fire Protection Program Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.24 Systems NCV 05000482/2024001-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to maintain a fire protection program procedure. Specifically, the licensee failed to maintain procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, to perform the required 18-month post-fire safe shutdown normal/bypass (isolation) switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.

Description:

The inspectors reviewed the licensees Updated Safety Analysis Report (USAR),off normal procedures, and surveillance procedures for the normal/bypass (isolation) switches for the train B essential service water system motor-operated valves that are credited for post-fire safe shutdown to determine the required surveillance testing. Specifically, the inspectors reviewed three off normal procedures including: procedure OFN RP-017, Control Room Evacuation, revision 56; procedure AP 10-100, Fire Protection Program, revision 26; and procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, and identified the following:

• Procedure AP 10-100, step 6.3.12.3, stated, in part that all STN RP-002 series of procedures are performed at least once per 18-months to verify the operability of normal/bypass (isolation) switches credited for post-fire safe shutdown that are used to bypass circuits that could be affected by a fire.

• Off normal procedure OFN RP-017 was used to determine the operability of credited post-fire safe shutdown B essential service water motor-operated valves that are operated by normal/bypass (isolation) switches located at the 480 volt motor control centers, which included train B essential service water from component cooling water heat exchanger motor-operated isolation valve, EFHV0060. The required position of EFHV0060 for post-fire safe shutdown was maintain/close to ensure adequate essential service water flow to all train B components required for post-fire safe shutdown.

• Procedure STN RP-002H was utilized to verify the operability of train B essential service water to and from the component cooling water heat exchanger B. However, EFHV0060 isolation switch, that was used to bypass circuits that could be affected by a fire in the control room, was not being testing every 18 months.

From the above, the inspectors determined that the licensee failed to perform the 18-month surveillance testing to verify the operability of the normal/bypass (isolation) switch credited for postfire safe shutdown for valve EFHV0060 in accordance with procedure AP 10-100, step 6.3.12.3. The inspectors informed the licensee of the issue. The licensee then entered it into their corrective action program as condition report 10029354. The licensee confirmed valve EFHV0060 normal/bypass (isolation) switch was not being testing every 18 months and was last tested March 2014. Valve EFHV0060 normal/bypass (isolation) switch was installed in 2013 at its 480 volt motor control center in accordance with change package 13898, and the licensee failed to identify that procedure STN PR-002H was required to be updated to ensure valve EFHV0060 normal/bypass (isolation) switch was tested every 18 months.

Corrective Action: The licensee performed an extent of condition review, established an hourly fire watch for the control room, and revised procedure STN RP-002H to perform 18-month surveillance testing for valve EFHV0060 normal/bypass (isolation) switch during RF 26.

Corrective Action Reference: Condition reports 10029354 and 10031492

Performance Assessment:

Performance Deficiency: The licensees failure to maintain procedure STN RP-002H to perform required fire protection program 18-month isolation/bypass surveillance testing for valve EFHV0060 normal/bypass (isolation) switch, was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the procedural quality attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensees failure to maintain procedural guidance to perform required 18-month isolation/bypass surveillance testing for valve EFHV0060 normal/bypass (isolation) switch prevented the licensee from verifying the valve was capable of being/maintained closed from the motor control center in a case of a fire in the control room.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix F, Fire Protection Significance Determination Process. The inspectors assigned the finding a fire category 1.4.7, because the finding involved post-fire safe shutdown. The inspectors determined that the finding had very low safety significance (Green) because the finding did not adversely affect the ability to reach and maintain hot shutdown/hot standby or safe and stable conditions using the credited safe shutdown success path.

Cross-cutting Aspect: Not present performance. Specifically, the performance deficiency occurred in 2013 when the licensee modified the motor control center for EFHV0060 to provide the isolation/bypass circuit to allow for local operation and failed to update procedure STN RP-002H.

Enforcement:

Violation: Technical Specification 5.4.1.d requires that written procedures shall be established, implemented, and maintained covering fire protection program implementation.

Procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, verified the operability of train B essential service water motor-operated valves for the component cooling water heat exchanger B isolation switch used to bypass circuits that could be affected by a fire.

Contrary to the above, from March 2014 to January 2024, the licensee failed to maintain a procedure covering the fire protection program implementation. Specifically, the licensee failed to maintain procedure STN RP-002H to perform the required 18-month isolation/bypass switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section

Bypass Reactor Trip Breaker Cornerstone Report Section Mitigating Green [H.5] Work Systems Open/Closed

Specification 5.4.1.a for the licensee failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification

order (WO) 18-444075-000, the licensee installed a vendor overhauled reactor trip breaker as train B reactor trip bypass breaker (BYB), and during RF 24 (March 25 May 9, 2021) the

Following being placed in the RTA position, on April 28, 2021, the breaker failed surveillance procedure STS IC-215, Trip Actuating Device Operational Test, Trip and Bypass Breaker UV/Shunt Trip, Turbine Trip on Reactor Trip and 4, revision 17. Specifically, the reactor trip breaker failed to generate the turbine trip signal associated with the -4 interlock

equipment performance evaluation.

The inspectors reviewed WO 18-444075-000, WO 20-259184-000, CR 10004991, CR 10005013, the past operability and equipment performance evaluation, technical specifications and identified the following:

• The reactor trip P-4 interlock requirements to meet Technical Specification 3.3.2, Engineering Safety Feature Actuation System (ESFAS) Instrumentation, limited condition of operation (LCO) F are two operable trains of reactor trip P-4 interlock. The functions of the reactor trip P-4 interlock was to prevent excessive cool down of the reactor coolant system following a reactor trip and the following was required to meet the LCO:

(1) trip the main turbine - Modes 1 and 2,

(2) isolate main feedwater with coincident low reactor coolant average temperature - Modes 1 and 2,

(3) allows manual block of the automatic re-actuation of safety injection after a manual reset of safety injection - Modes 1, 2, and 3,

(4) prevents opening of the main feedwater isolation valves if closed on safety injection and steam generator water level high-high - Modes 1, 2, and 3.

• The equipment performance evaluation and the past operability determined the turbine trip did not function because two wires connecting the trip contact, as seen on drawing M-766-01045, to the test points and TB4 terminals 1 and 4, as seen on drawing M-766-1043, were not installed during the breakers overhaul performed by a vendor. This issue was identified during the performance of surveillance procedure STS IC-215 The function of the trip contact was to produce a turbine trip signal from the P-4 interlock upon a reactor trip breaker opening. Additionally, between August 18, 2020, and RF 24, BYB was racked to connect for testing of RTB on October 10, 2020, and February 4, 2021, for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the 48-hour completion time for LCO 3.3.2 condition F in support of train B reactor trip breaker quarterly testing.

During these periods, if a reactor trip occurred by BYB, no turbine trip signal would have been generated from the P-4 interlock, however, RTA was fully capable of generating the required turbine trip, so no complete loss of safety function occurred.

The equipment performance evaluation and past operability documented in CRs 10004991 and 10005013 did not review the maintenance practice of installing and performing maintenance on reactor trip breakers in Mode 1, nor did it contain corrective actions associated with the maintenance practice.

• The installation WO 18-445075-000 stated to perform maintenance on the spare reactor trip breaker in accordance with maintenance procedure MPE M766Q-03, Reactor Trip Switchgear Breaker, revision 24, and perform as found and as left testing in accordance with surveillance procedure STS IC-746, Reactor Trip and Bypass Breaker Response Time Testing, revision 2C. The purpose of surveillance procedure STS IC-746 was to perform response time testing on train A and B reactor trip breakers and bypass reactor trip breakers which does not test all the technical specification design functions, including the reactor trip P-4 interlocks.

The inspectors concluded the licensee did not properly pre-plan maintenance and installation of overhauled reactor trip breakers in Mode 1 to ensure adequate post-maintenance testing was performed to demonstrate full technical specification operability.

Corrective Actions: The licensee initiated actions to review what modes of operation are appropriate for performing maintenance, installation, and testing of reactor trip breakers.

Corrective Action References: Condition reports 10031001 and 10031493

Performance Assessment:

Performance Deficiency: The licensees failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the equipment performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, failure to perform the appropriate post-maintenance testing prevented the licensee from identifying the train B bypass reactor trip breaker P-4 interlock was inoperable.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be of very low safety significance (Green) because it

(1) was not a deficiency affecting design or qualification of a mitigating system,

(2) does not represent a loss of the probability risk analysis (PRA) function of a single train technical specification system for greater than allowed outage time,

(3) does not represent a loss of PRA function of one train of a multi-train technical specification for greater than its allowed outage time, (4)does not represent a loss of the PRA function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

(5) does not represent a loss of PRA system and/or function as defined by the plant risk information e-book or licensees PRA for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

(6) does not result in the loss of a high safety-significant, nontechnical specification train for greater than 3 days.

Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, inappropriately planning the installation of vendor overhauled reactor trip breakers in Mode 1 prevented the licensee from performing adequate post-maintenance testing to verify proper operation of the reactor trip breaker in the bypass location to ensure it was fully operable.

Enforcement:

Violation: Technical Specification 5.4.1.a, requires, in part, that written procedures be established, implemented, and maintained covering applicable procedures recommended in appendix A to Regulatory Guide 1.33, Quality Assurance Program Requirements, revision 2, dated February 1978. Regulatory Guide 1.33, appendix A, section 9.a, requires, in part, maintenance that can affect the performance of safety-related equipment should be properly pre-planned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Work order 18-445075-000 pre-planned the maintenance and installation of reactor trip bypass breaker B.

Contrary to the above, between August 2020 to March 2021, the licensee failed to properly pre-plan and perform maintenance that affected safety-related equipment. Specifically, WO 18-445075-000 failed to provide appropriate instructions for safety-related bypass reactor trip breaker post-maintenance testing following maintenance and installation to verify the breaker was fully operable, by testing the technical specification required P-4 interlock.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 4, 2024, the inspectors presented the integrated inspection results to R. Bayer, General Manager, Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action Condition Reports 10029393, 10029523, 10029546

Documents

71111.01 Drawings M-12BN01 Piping and Instrumentation Diagram Borated Refueling 20

Water Storage Tank

71111.01 Drawings M-12EC02 Piping and Instrumentation Diagram Fuel Pool Cooling and 7

Clean-Up System

71111.01 Procedures AI 14-006 Severe Weather 19

71111.01 Procedures ALR 00-055F FRZ Prot Trouble 13

71111.01 Procedures STS CH-021 Spent Fuel Pool Boron Concentration Determination 9A

71111.01 Procedures SYS EC-121 Recirc of the RWST Through the Fuel Pool Cleanup System 21

71111.01 Procedures SYS EF-205 ESW/CIRC Water Cold Weather Operations 43

71111.01 Work Orders WO 39464

71111.04 Calculations XX-E-004 AC Motor Operated Valve Minimum Terminal Voltage 14

71111.04 Calculations XX-E-009 System NB, NG, PG Undervoltage/Degraded Voltage Relay 1

Setpoints

71111.04 Corrective Action Condition Reports 10009424, 10028903, 10028925

Documents

71111.04 Corrective Action Condition Report 10030450

Documents

Resulting from

Inspection

71111.04 Drawings E-018-0852 MMC Cubicles SZ 5 2SP-1WD Schematic W12

71111.04 Drawings E-018-0853 Wiring Diagram 2SP IWD (Size 5) W12

71111.04 Drawings E-11NG01 Low Voltage System Class 1E 480V Single Line Meter and 17

Relay Diagram

71111.04 Drawings E-11NG02 Low Voltage System Class 1E 480 V. Single Line Meter and 17

Relay Diagram

71111.04 Drawings E-11NG20 Low Voltage System Class 1E Motor Control Center 318

Summary

71111.04 Drawings E-13EF09A Schematic Diagram ESW To/From Containment Air Coolers 1

Isolation Valve

71111.04 Drawings E-13GN02A Schematic Diagrams Containment Cooler B and D 18

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings E-13NG01A Low Voltage System Class 1E 480 V Three Line Meter and 6

Relay Diagram

71111.04 Drawings E-1F9915 Design Basis Document for OFN RP-017, Control Room 15

Evacuation

71111.04 Drawings KD-7496 One Line Diagram 46

71111.04 Drawings M-12AB01 Piping and Instrumentation Diagram Main Steam System 17

71111.04 Drawings M-12AB02 Piping and Instrumentation Diagram Main Steam System 15

71111.04 Drawings M-12AE02 Piping and Instrumentation Diagram Feedwater System 19

71111.04 Drawings M-12AL Piping and Instrumentation Diagram Auxiliary Feedwater 33

System

71111.04 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 33

System

71111.04 Drawings M-12BM01 Piping and Instrumentation Diagram Steam Generator 20

Blowdown Sys.

71111.04 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Basis Document 13

71111.04 Procedures AI 21-016 Operator Time Critical Actions Validation 25

71111.04 Procedures ALR 00-025E NG02 Bus Trouble 12

71111.04 Procedures AP 21-004 Operator Response Time Program 5A

71111.04 Procedures BD-EMG E-0 Reactor Trip or Safety Injection 31

71111.04 Procedures BD-EMG E-2 Faulted Steam Generator Isolation 15

71111.04 Procedures CKL AL-120 Auxiliary Feedwater Normal Lineup 44A

71111.04 Procedures EMG E-0 Reactor Trip or Safety Injection 46

71111.04 Procedures EMG E-2 Faulted Steam Generator Isolation 24A

71111.04 Procedures EMG FR-S1 Response to Nuclear Power Generation/ATWS 25

71111.04 Procedures OFN RP-17 Control Room Evacuation 56

71111.04 Procedures STN RP-002G ESW Train B to CTMT Air Cooler ISO Switch 3

71111.04 Procedures SYS GK-201 Mitigating Actions for Inoperable SGK05 Train 21D

71111.04 Procedures SYS NG-332 Deenergized NG02 NG04 and NG06E 29A

71111.04 Work Orders WO 15194, 21-475048-000, 21-475048-001

71111.05 Calculations XX-X-004 Combustible Fire Loading for Each in the Various Fire Areas 5

at WCNOC

71111.05 Corrective Action Condition Reports 10009424, 10029354

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Corrective Action Condition Reports 10030120, 10030121

Documents

Resulting from

Inspection

71111.05 Drawings E-11NG20 Low Voltage System Class 1E Motor Control Center 318

Summary

71111.05 Drawings M-12EF02 Piping and Instrumentation Diagram Essential Service Water 45

System

71111.05 Miscellaneous E-1F9905 Fire Hazard Analysis 11

71111.05 Miscellaneous E-1F9910 Post Fire Safe Shutdown Area Analysis 17

71111.05 Miscellaneous PT12386 Post Fire Safe Shutdown Issue 0

71111.05 Miscellaneous WCRE-35 Boundary Matrix 11

71111.05 Procedures ALR KC-888 Fire Protection Panel KC-008 Alarm Response 35

71111.05 Procedures AP 10-100 Fire Protection Program 26

71111.05 Procedures AP 10-101 Control of Transient Ignition Sources 27

71111.05 Procedures AP 10-102 Control of Combustible Materials 27

71111.05 Procedures AP 10-103 Fire Protection Impairment Control 41

71111.05 Procedures AP 10-104 Breach Authorization 40

71111.05 Procedures AP 10-105 Fire Protection Training and Drills 24B

71111.05 Procedures AP 10-106 Fire Preplan 24

71111.05 Procedures AP 26C-004 Operability Determination and Functionality Assessments 48

71111.05 Procedures OFN KC-016 Fire Responses 54

71111.06 Calculations XX-M-069 FAC Program Minimum Wall Thickness Calculation for 6

Large Bore Piping and Components

71111.06 Corrective Action Condition Reports 10019400, 10020468, 10021613, 10021652, 10027094,

Documents 10028389, 10029850

71111.06 Drawings M-12AE01 Piping and Instrumentation Diagram Feedwater System 53

71111.06 Drawings M-12AE02 Piping and Instrumentation Diagram Feedwater System 19

71111.06 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 33

System

71111.06 Drawings M-13AE05 Piping Isometric Main Feedwater Reactor and Auxiliary 14

Building

71111.06 Miscellaneous MS-02 Pipe Class Sheets 65

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.06 Procedures EMG E-2 Faulted Steam Generator Isolation 24A

71111.11Q Procedures EMG E-0 Reactor Trip or Safety Injection 46

71111.11Q Procedures EMG ES-02 Reactor Trip Response 42

71111.11Q Procedures GEN 00-004 Power Operation 102

71111.11Q Procedures GEN 00-005 Minimum Load to Hot Standby 96

71111.11Q Procedures STS RE-006 EOL Core MTC Measurement 22

71111.12 Calculations XX-E-004 AC Motor Operated Valve Minimum Terminal Voltage 14

71111.12 Calculations XX-E-042 Class 1E 480V AC and 208/120V AC System Coordination 0

71111.12 Corrective Action Condition Reports 73120, 73421, 81790, 10004991, 10005001, 10005013,

Documents 10007665, 10013896, 10014094, 10018253, 10019416,

10020251, 10020290, 10023534, 10023559, 10024112,

10024908, 10026422, 10026451, 10026459, 10026498,

10027058, 10027518, 10027877, 10028066, 10028432,

10028903, 10028925, 10029210, 10029729, 10029830,

10029484

71111.12 Corrective Action Condition Report 10030449

Documents

Resulting from

Inspection

71111.12 Drawings E-025-00007 ESW Screen B Spray EFHV0092 W14

sheet 201

71111.12 Drawings E-11NG20 Low Voltage System Class 1E Motor Control Center 318

Summary

71111.12 Drawings E-13NG02 Schematic Diagram Containment Cooler Fans A and C 17

71111.12 Drawings M-12AB01 Piping and Instrumentation Diagram Main Steam System 17

71111.12 Drawings M-766-01043 05W

71111.12 Engineering CP 14923 Restore Regulatory Compliance for Ten 480V MOVs 0

Changes

71111.12 Miscellaneous 2013-049 USAR Change Request 12/12/2013

71111.12 Miscellaneous E-018A-00007 Instruction Manual for Molded Case Circuit Breaker W15

71111.12 Miscellaneous QL-AB System AB Main Steam System 11

71111.12 Miscellaneous WCLR-33 Electrical Cable Connections Not Subject to 10 CFR 50.49 4

Environmental Qualification Requirements B2.1.36

NUREG-1801 Program XLE6 Aging Management Program

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Miscellaneous WCNOC-76 Medium Low Voltage AC and Low Voltage DC Overcurrent 8

Protection Coordination for Wolf Creek Generating Station

71111.12 Miscellaneous WCQPM Wolf Creek Quality Program Manual 13

71111.12 Procedures AI 16B-002 Preventive Maintenance Change Process 21

71111.12 Procedures AP 16B-003 Planning and Scheduling Preventive Maintenance 8B

71111.12 Procedures AP 16E-002 Post Maintenance Testing Development 21B

71111.12 Procedures AP 24D0-003 Receipt Inspection 18

71111.12 Procedures I-ENG-005 Infrared Thermography 12

71111.12 Procedures MGE EOOP-11 Molded Case Circuit Breaker and Ground Fault Sensor 38

Testing

71111.12 Procedures STS IC-211A Actuation Logic Test Train A Solid State Protection System 37A

71111.12 Procedures STS IC-211B Actuation Logic Test Train B Solid State Protection System 38A

71111.12 Procedures STS IC-215 TADOT of Manual Reactor Trip, Trip and Bypass Breaker 17

UV/Shunt Trip, Turbine Trip on Reactor Trip and P4

71111.12 Procedures STS MT-024A Functional Test of 480 and 120 Volt Molded Case Circuit 16A

Breakers

71111.12 Work Orders WO 12580, 14-385283-000, 14-385283-001, 15-406874-000,

18-439151-000, 18-445075-000, 19-452140-026,

20-458342-000, 20-460120-000, 20-460914-000,

2-480055-000, 22-477183-000, 22-477957-001,

23-486740-000, 23-486740-001, 23-488067-000

71111.13 Corrective Action Condition Reports 10029736, 10030624, 10030630, 10030631, 10030667,

Documents 10030732, 10030733, 10030734, 10030736, 10030739,

10031127

71111.13 Corrective Action Condition Report 10029882

Documents

Resulting from

Inspection

71111.13 Drawings M-12AB01 Piping and Instrumentation Diagram Main Steam System 17

71111.13 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 33

System

71111.13 Drawings M-12BG03 Piping and Instrumentation Diagram Chemical and Volume 52

Control System

71111.13 Drawings M-12EM01 Piping and Instrumentation Diagram High Pressure Coolant 49

Inspection Type Designation Description or Title Revision or

Procedure Date

Injection System

71111.13 Drawings M-12FC02 Piping and Instrumentation Diagram Auxiliary Turbines 25

Auxiliary Feedwater Pump Turbine

71111.13 Drawings M-12KA05 Piping and Instrumentation Diagram Compressed Air 7

System

71111.13 Miscellaneous E-1F9910 Post-Fire Safe Shutdown Area Analysis 17

71111.13 Procedures AI 16C-006 Troubleshooting 12A

71111.13 Procedures AI 22C-013 Protected Equipment Program 26

71111.13 Procedures AI 22C-014 TSEO Management 7A

71111.13 Procedures AP 22C-003 On-Line Nuclear Safety and Generation Risk Assessment 29

71111.13 Procedures EMG ES-12 Transfer to Cold Leg Recirculation 25

71111.13 Procedures OFN RP-017 Control Room Evacuation 56

71111.13 Procedures STS KA-010 N2 Accumulator Inservice Check Valve Test 20

71111.13 Procedures SYS EM-003 Operation of EM HV-8924 4

71111.13 Procedures SYS KJ-200 Inoperable Emergency Diesel 35

71111.13 Procedures SYS NB-202 Transferring NB02 Power Sources 62

71111.13 Work Orders WO 50424, 50426, 50948

71111.15 Calculations AN-05-016 Wolf Creek MSLB Containment Pressure and Temperature 0

Response Analyses with GOTHIC for the MSIV/MFIV

Replacement Project

71111.15 Calculations SA-91-016 ECCS Design Basis Injection Flowrates Re-analysis in 0

Supporting of the WCGS Power Re-Rate Project

71111.15 Calculations XX-M-069 FAC Program Minimum Wall Thickness Calculation for 6

Large Bore Piping and Components

71111.15 Corrective Action Condition Reports 99-3942, 10019400, 10021613, 10028389, 10028779,

Documents 10029850, 10030351

71111.15 Drawings M-12BG03 Piping and Instrumentation Diagram Chemical and Volume 52

71111.15 Drawings M-12EM01 Piping and Instrumentation Diagram High Pressure Coolant 49

Injection System

71111.15 Drawings M-622.1A-00001 SGK05A and SGK05B Air Conditioner Refrigeration W13

Schematic

71111.15 Engineering DCP 09488 Governor Replacement of Emergency Diesel Generators 15

Changes

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Miscellaneous M-018B-00009 Woodward Governor Failure Analysis and Test Report W01

Review

71111.15 Miscellaneous M-10AE Feedwater System 2

71111.15 Miscellaneous MS-02 Pipe Class Sheets 65

71111.15 Procedures AP 26C-004 Operability Determinations and Functionality Assessments 48

71111.15 Procedures DB-EMG E-0 Reactor Trip or Safety Injection 31

71111.15 Procedures EMG E-0 Reactor Trip or Safety Injection 46

71111.15 Procedures EMG E-2 Faulted Steam Generator Isolation 24A

71111.15 Procedures EMG E-3 Steam Generator Tube Rupture 41

71111.15 Procedures EMG ES-12 Transfer to Cold Leg Recirculation 25

71111.15 Procedures MPE GK-004 GK Unit Preparation for Work 12

71111.15 Procedures STS KJ-005B Manual/Auto Start, Sync and Loading of EDG NE02 72

71111.15 Procedures SYS EM-003 Operation of EM HV-8924 4

71111.15 Work Orders WO 27285, 33185, 48154, 22-482755-000

71111.18 Calculations BN-20 RWST Volumes and Level Set Points 5

71111.18 Calculations BN-M-013 Time Available for Injection, ECCS, and Containment Spray 4

Pumps Transfer and Evaluation of Air Entrainment at Empty

Alarm

71111.18 Calculations EJ-30 RHR Pumps A and B NPSH 3

71111.18 Calculations EN-33 Containment Spray Pump NPSH 2

71111.18 Calculations FL-18 Containment Flood Levels for LOCA and MSLB 5

71111.18 Calculations WES-009-CALC- Wolf Creek/Callaway Post-LOCA Containment Water Level 1

001 Calculation

71111.18 Corrective Action Condition Reports 121822, 137915, 142204, 10014808, 10015112, 10015262,

Documents 10017090, 10017620, 10019464, 10019626, 10030624,

10030630, 10030361, 10030650, 10030662, 10030663,

10030664,

71111.18 Corrective Action Condition Report 10029963

Documents

Resulting from

Inspection

71111.18 Engineering DECP 020631 System Descriptions M-10BN and M-10EN Update 0

Changes

71111.18 Engineering DRE 20456 AV1 Positioner Gauge Block Removal 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Changes

71111.18 Miscellaneous DB-EMG ES-12 Transfer to Cold Leg Recirculation 18

71111.18 Miscellaneous SQTS-01-GSQTP Seismic Functional Procedure 5

71111.18 Procedures ALR 00-047C RWST LOLO2 12

71111.18 Procedures AP 05-021 Direct Replacement Equivalency 6A

71111.18 Procedures AP 26C-004 Operability Determination and Functionality Assessments 48

71111.18 Procedures DB-EMG ES-03 SI Termination 18

71111.18 Procedures EGM ES-03 SI Termination 29

71111.18 Procedures EMG E-0 Reactor Trip or Safety Injection 46

71111.18 Procedures EMG ES-12 Transfer to Cold Leg Recirculation 25

71111.20 Corrective Action Condition Report 10030086, 10030789, 10031067

Documents

71111.20 Miscellaneous Interoffice Refuel 26 Risk Assessment Team Report - Schedule Rev. 02/22/2024

Correspondence C 1/12/2024

71111.20 Procedures AP 22B-001 Outage Risk Management 22

71111.20 Procedures GEN 00-006 Hot Standby to Cold Shutdown 106

71111.20 Procedures STS BB-011 Reactor Coolant System and Pressurizer Heatup/Cooldown 35

Surveillance

71111.20 Procedures STS IC-901 Channel Operational Test Reactor Coolant Cold 23A

Overpressure Protection Instrumentation

71111.20 Procedures SYS NB-202 Transferring NB02 Power Sources 62

71111.20 Work Orders WO 53004, 20-466498-000, 21-474062-000, 23-487901-000

71111.24 Calculations XX-M-080 Wolf Creek Generating Station Pump Room Heat-Up 1

Analysis

71111.24 Corrective Action Condition Reports 20559, 10001214, 10004589, 10005013, 10007337,

Documents 10019205, 10024045, 10024821, 10028295, 10028635,

10028649, 10029512, 10029662, 10029726, 10029748,

10030191, 10030273, 10030274, 10030624, 10030630,

10030361

71111.24 Corrective Action Condition Reports 10029354, 10029485, 10029495, 100300455, 10031001,

Documents 10031492, 10031493

Resulting from

Inspection

71111.24 Drawings E-13EF09A Schematic Diagram ESW To/From Containment Air Coolers 1

Inspection Type Designation Description or Title Revision or

Procedure Date

Isolation Valve

71111.24 Drawings E-13NN01 Class 1E Instrument AC Schematic 11

71111.24 Drawings M-12AB01 Piping and Instrumentation Diagram Main Steam System 17

71111.24 Drawings M-12AL01 Piping and Instrumentation Diagram Auxiliary Feedwater 33

System

71111.24 Drawings M-12EF01 Piping and Instrumentation Diagram Essential SVC Water 30

System

71111.24 Drawings M-12EF02 Piping and Instrumentation Diagram Essential Service Water 45

System

71111.24 Drawings M-12KA05 Piping and Instrumentation Diagram Compressed Air 7

System

71111.24 Miscellaneous E-1F9915 Design Basis Document for OFN RP-017, Control Room 15

Evacuation

71111.24 Miscellaneous WCRE-34 Fourth 10-Year Interval Inservice Testing Bases Document 13

71111.24 Procedures AP 10-100 Fire Protection Program 26

71111.24 Procedures AP 16E-002 Post Maintenance Testing Development 21B

71111.24 Procedures AP 26C-004 Operability Determination and Functionality Assessments 48

71111.24 Procedures AP 26C-004 Operability Determination and Functionality Assessments 26C

71111.24 Procedures AP 29B-002 ASME Code Testing of Pumps and Valves 12A

71111.24 Procedures AP 29B-003 Surveillance Testing 18

71111.24 Procedures EMG E-0 Reactor Trip or Safety Injection 46

71111.24 Procedures EMG E-2 Faulted Steam 24A

71111.24 Procedures EMG E-3 Steam Generator Tube Rupture 41

71111.24 Procedures MPE 766Q-008 Cleaning and Inspection of Class 1E Inverters 0

71111.24 Procedures MPE RC-001 Room Cooler Maintenance 13

71111.24 Procedures OFN RP-017 Control Room Evacuation 56

71111.24 Procedures STN AL-201 Auxiliary Feedwater System Valve Test 9

71111.24 Procedures STN RP-001E ESW to SW SYS VLV ISO Switch 3A

71111.24 Procedures STN RP-001F ESW to UHS VLV ISO Switch 2A

71111.24 Procedures STN RP-002G ESW TRN B to CTMT Air Coolers ISO Switch 3

71111.24 Procedures STN RP-002H ESW TRN B to CCW HX B ISO Switch 2

71111.24 Procedures STN RP-011E ESW to SW SYS VLV ISO Switch 10 YR 1

71111.24 Procedures STN RP-011F ESW to UHS VLV ISO Switch 10 YR 1

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.24 Procedures STN RP-012H ESW To/From CCW HX B ISO Switches 10 year 2

71111.24 Procedures STN TCA-001 Manual Time Critical Action Timing 7

71111.24 Procedures STS AB-201D Atmospheric Relief Valve Inservice Valve Test 31

71111.24 Procedures STS AL-103 TDAFW Pump Inservice Pump Test 76

71111.24 Procedures STS AL-201C Turbine Driven Auxiliary Feedwater System Inservice Valve 13

Test

71111.24 Procedures STS EF-100B ESW System Inservice B and ESW Check Valve B Test 51A

71111.24 Procedures STS GN-001 CTMT Cooling Fan Operability Test 11

71111.24 Procedures STS IC-746 Reactor Trip and Bypass Breaker Response Time Testing 2C

71111.24 Procedures STS KA-010 N2 Accumulator Inservice Check Valve Test 20

71111.24 Procedures STS PE-007 Periodic Verification of Motor Operated Valves 5A

71111.24 Procedures SYS KJ-124 Post Maintenance Run of Emergency Diesel Generator B 76

71111.24 Procedures SYS NN-131 Energizing NN Buses 28

71111.24 Procedures SYS NN-200A Transferring NN01 and NN03 Buses Between Power 1

Sources

71111.24 Work Orders WO 15194, 15202, 15925, 16321, 16774, 16776, 16778, 16790,

16794, 16800, 16880, 16886, 17423, 17435, 17442, 17549,

17553, 26620, 27203, 29104, 30569, 32367, 32797, 32392,

38854, 44708, 45373, 50424, 50426, 50431, 17-430071-

003, 18-444963-000, 18-444964-000, 18-445168-000,

18-445169-000, 19-448878-000, 19-488879-000,

19-448880-000, 19-448882-000, 22-480055-000,

23-146046-000, 23-485690-000, 23-486898-000,

23-486898-001, 23-489131-005

71152A Corrective Action Condition Reports 14364, 45434, 50217, 1996-0015, 1995-3074, 10029354,

Documents 10004991, 10004995, 10005013, 10017445

71152A Corrective Action Condition Report 10030907

Documents

Resulting from

Inspection

71152A Drawings M-766-01043 W05

71152A Drawings M-766-01045 W04

71152A Miscellaneous EPR NS30650022 06/05/2009

71152A Miscellaneous WCQPM Wolf Creek Quality Program Manual 13, 14

Inspection Type Designation Description or Title Revision or

Procedure Date

71152A Procedures AP 24-002 Requisition and Procurement Process 30E

71152A Procedures AP 24D-003 Receipt Inspection 18

71152A Procedures OFN RP-013 Control Room Not Habitable 23

71152A Procedures OFN RP-017 Control Room Evacuation 56

71152A Procedures STN RP 002D BIT Inlet VLV B ISO Switch 6

71152A Procedures STN RP-001C VCT Outlet Isolation VLV ISO Switch 2

71152A Procedures STN RP-001D CCP B Suct from RWST VLV ISO Switch 2B

71152A Procedures STN RP-001N SGL15B Control RM ISO Switch 1

71152A Procedures STN RP-002C RWST to RHR B Suction ISO Switch 4

71152A Procedures STN RP-002F CCP B Recirc VLV ISO Switch 5

71152A Procedures STN RP-002I CCW TRN B SPLY/Return VLV ISO Switch 2

71152A Procedures STN RP-011C VCT Outlet Isolation VLV ISO Switch 10 YR 1

71152A Procedures STN RP-011D CCP B Suct from RWST VLV ISO Switch 10 YR 1

71152A Procedures STN RP-011N SGL15B Control RM ISO Switch 10 YR 3

71152A Procedures STN RP-012C RWST to RHR Pump B Suction ISO Switch 10 YR 2

71152A Procedures STN RP-012D BIT Inlet VLV B ISO Switch 10 YR 3

71152A Procedures STN RP-012F CCP B Recirc VLV ISO Switch 10 YR 3

71152A Procedures STN RP-012I CCW TRN B SPLY/Return VLV ISO Switch 10 YR 1

71152A Procedures STS IC-211B Actuation Logic Test Train B Solid Sate Protection System 38A

71152A Procedures STS IC-215 TADOT of Manual Reactor Trip, Trip and Bypass Breaker 17

UV/Shunt Trip, Turbine Trip on Reactor Trip and P4

71152A Procedures STS IC-610B Slave Relay Test K610 Train B Safety Injection 21

71152A Work Orders WO 13-378440-000, 15-406873-002, 21-469167-000,

21-472626-000, 21-474139-000, 22-483407-000,

2-477183-000

24