IR 05000482/2022001

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Integrated Inspection Report 05000482/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200079/2022001
ML22109A144
Person / Time
Site: Peach Bottom, Wolf Creek  Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 04/25/2022
From: Greg Werner
NRC/RGN-IV/DORS
To: Reasoner C
Wolf Creek
References
IR 2022001
Download: ML22109A144 (35)


Text

April 25, 2022

SUBJECT:

WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2022001 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200079/2022001

Dear Mr. Reasoner:

On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On April 7, 2022, the NRC inspectors discussed the results of this inspection with Mr. Jaime McCoy, Site Vice President, and other members of your staff.

The results of this inspection are documented in the enclosed report.

Three findings of very low safety significance (Green) are documented in this report. All 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, Gregory E. Werner, Chief Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 and 07200079 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket Number:

05000482 and 07200079

License Number:

NPF-42

Report Number:

05000482/2022001 and 07200079/2022001

Enterprise Identifier:

I-2022-001-0007 and I-2022-001-0094

Licensee:

Wolf Creek Nuclear Operating Corporation

Facility:

Wolf Creek Generating Station

Location:

Burlington, KS

Inspection Dates:

January 1, 2022 to March 31, 2022

Inspectors:

L. Brookhart, Senior Spent Fuel Storage Inspector

W. Cullum, Reactor Inspector

C. Henderson, Senior Resident Inspector

D. Reinert, Reactor Inspector

E. Simpson, Health Physicist

J. Vera, Resident Inspector

Approved By:

Gregory E. Werner, Chief

Projects Branch B

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection and an independent spent fuel storage installation 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 Establish Fire Compensatory Measure During Maintenance Activities Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-01 Open/Closed

[P.3] -

Resolution 71111.05 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to implement the fire protection program procedure requirements. Specifically, the licensee failed to implement appropriate fire compensatory measures during planned maintenance activities that prevented a fire and halon boundary door from self-closing and latching due to ventilation airflow.

Failure to Correct Inadequate Procedural Guidance Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-02 Open/Closed

[P.5] -

Operating Experience 71111.12 The inspectors reviewed a self-revealed Green finding and associated non-cited violation of Technical Specification 5.4.1.a, for the licensees failure to properly pre-plan and perform maintenance that can affect the performance of safety-related equipment. Specifically, the licensee failed to correct inadequate procedural guidance associated with filling and venting the emergency diesel generator jacket water and intercooler system following planned maintenance. This condition resulted in air binding the emergency diesel generator A jacket water keep warm pump, resulting in jacket water leakage greater than allowed to support emergency diesel generator operability.

Failure to Schedule Preventive Maintenance to Prevent Unacceptable Preconditioning Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-03 Open/Closed None (NPP)71111.22 The inspectors identified a Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensee failure to accomplish instructions, procedures, or drawings appropriate to the circumstances that would have prevented unacceptable preconditioning of the 125 Vdc battery chargers. Specifically, the licensee failed to accomplish Procedure AI 29B-003, Guidance to Prevent Unacceptable Preconditioning Prior to Testing,

Revision 2, to not schedule preventive maintenance prior to conducting as-found 125 Vdc battery charger technical specification surveillance testing. This resulted in three examples of unacceptable preconditioning the 125 Vdc battery chargers.

Additional Tracking Items

None.

PLANT STATUS

Wolf Creek Generating Station began the inspection period at full power. On February 11, 2022, the licensee reduced power to 62 percent at the request of the transmission system operator to facilitate unplanned outage of the 345 kV Benton Line and was returned to full power on February 12, 2022. On March 24, 2022, the licensee reduced power to 62 percent at the request of transmission system operator to facilitate planned maintenance outage of the 345 kV Rose Hill line and was returned to full power on March 25, 2022. On three occasions during the quarter the licensee reduced power to 70 percent for flexible power operations (based on daily market demand) and returned to full power after each occasion.

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, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:

Trains A and B battery rooms and station blackout diesel generators batteries on February 16, 2022

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

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

(1) Train A dc distribution system alignment during Class 1E air conditioning maintenance outage on January 19, 2022
(2) Emergency diesel generator A jacket water makeup using essential service water system on January 25, 2022
(3) Emergency diesel generator A lube system standby condition on January 26, 2022
(4) Train A containment spray following technical specification equipment outage restoration on February 18, 2022
(5) Train B residual heat removal during train A technical specification equipment outage restoration on March 23, 2022

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

(1) The inspectors evaluated system configurations during a complete walkdown of the dc distribution system on March 9, 2022.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) DC switchgear room number 2, fire area C-15, on January 27, 2022
(2) DC switchboard room number 4 door was not automatically closing and latching during train A Class 1E air conditioning unit maintenance, fire area C-15, on January 27, 2022
(3) Turbine-driven auxiliary feedwater pump room, fire area A-15, on February 4, 2022
(4) Auxiliary feedwater pump valve compartment rooms, fire area A-30, on February 4, 2022
(5) Battery room number 4, fire area C-15, on February 16, 2022

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Removal of auxiliary building level 2026 and 2047 equipment hatches during train B component cooling water heat exchanger flush on March 15, 2022

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Train B Class 1E air conditioning heat exchanger tube plugging evaluation on February 17, 2022

71111.07T - Heat Exchanger/Sink Performance Heat Exchanger (Service Water Cooled) (IP Section 03.02)

The inspectors evaluated heat exchanger performance on the following:

(1) Train B containment cooler, SGN01B
(2) Train B Class 1E equipment room air conditioner, SGK05B
(3) Train A jacket water heat exchanger, EKJ06A

Ultimate Heat Sink Containment Device and Dam (IP Section 03.05) (1 Sample)

The inspectors evaluated the ultimate heat sink performance containment device and dam on the following:

(1) Ultimate heat sink underwater containment structure

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 down power to 62 percent reactor power to support 345 kV Rose Hill line maintenance outage on March 24, 2022.

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

(1) The inspectors observed and evaluated simulator training activities on March 8, 2022.

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) Train A Class 1E electrical equipment air conditioning compressor failure on March 10, 2022
(2) Train A and B dc distribution system maintenance effectiveness on February 18, 2022

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) Emergency diesel generator A jacket water keep warm pump shaft replacement commercial grade dedication on February 9, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) Emergent work for emergency diesel generator A jacket water leak repair on January 10, 2022
(2) Train A safety injection planned maintenance outage on January 12, 2022
(3) Train A Class 1E air conditioning planned maintenance outage on January 19, 2022
(4) Emergent work for train B engineered safety feature actuation system (ESFAS)balance of plant cabinet SA36E lower and upper 48 V power supply replacement on January 21, 2022
(5) Emergent work for train A load shedder and emergency load sequencer power supply replacement on February 7, 2022
(6) Emergency diesel generator B and essential service water B maintenance outage windows on February 28, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

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

(1) Emergency diesel generator A operability with the jacket water keep warm pump and heater isolated for emergent replacement of the shaft on January 12, 2022
(2) Train B balance of plant ESFAS cabinet SA036E loss of power operability determination on January 28, 2022
(3) Train B Class 1E air conditioning heat exchanger exceeds tube blockage limit during as-found inspections past operability determination on February 1, 2022 (4)
(5) Train A auxiliary feedwater system essential service water suction check valve degraded stem use as is operability evaluation on March 1, 2022 Train A load shedder and emergency load sequencers 48 V power supply fan failure and replacement operability determination on March 3, 2022
(6) Train B component cooling water heat exchanger during essential service water summer lineup operability determination on March 10, 2022
(7) Train B control room emergency ventilation system failure to meet surveillance testing acceptance criteria past operability determination on March 17, 2022

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Train B component cooling water heat exchanger flush temporary procedure on March 1, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

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

(1) Train A battery charger, NK23, card replacement post maintenance testing on February 7, 2022
(2) Emergency diesel generator A emergent replacement of the jacket water keep warm up shaft post-maintenance testing on February 9, 2022
(3) Train A containment spray pump technical specification equipment outage post-maintenance testing on February 10, 2022
(4) Train A Class 1E air conditioning system condenser heat exchanger inspection and cleaning and sensing line replacement post-maintenance testing on February 16, 2022
(5) Train A Class 1E air conditioning system relay replacement post-maintenance testing on February 16, 2022
(6) Train B balance of plant ESFAS cabinet SA36E power supply replacement post-maintenance testing on February 16, 2022

71111.22 - Surveillance Testing

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

Surveillance Tests (other) (IP Section 03.01) (4 Samples)

(1) Operational surveillance testing on 125 V battery charger on February 7, 2022
(2) Manual calculation of axial flux difference, thermal power, and power range adjustment to calorimetric with nuclear plant island structure computer nonfunctional February 17, 2022
(3) Weekly battery inspections and dc distribution system breaker alignment verification on February 28, 2022
(4) Manual calculation of reactor coolant system leakage rate during unavailability of the nuclear plant island structure computer on February 18, 2022

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Essential service water isolation to air compressor check valve EFV0046 on February 8, 2022

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Reactor coolant system unidentified leak rate elevated trend on March 28,

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, 2021 through December 31, 2021 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
(1) January 1, 2021 through December 31, 2021

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

(1) January 1, 2021 through December 31, 2021

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) Emergency diesel generator B lightbulb failure causing inoperability extent of condition review on March 15,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60855 - Operation of an ISFSI The inspectors performed a review of the licensees Independent Spent Fuel Storage Installation (ISFSI) activities to verify compliance with requirements of the Transnuclear (TN)

Nutec Horizontal Modular Extended Optimized Storage (NUHOMS EOS) system's Certificate of Compliance 72-1042, Amendment 1, and Final Safety Analysis Report (FSAR), Revision 3. The inspectors reviewed selected procedures, corrective action reports, and records to verify ISFSI operations were compliant with the Certificate's technical specifications, requirements in the FSAR, and NRC regulations.

Operation of an ISFSI===

(1) The inspectors evaluated the licensees dry cask storage operations, from January 17-21, 2022, during an onsite inspection. The ISFSI is located within the Part 50 reactor's protected area. The EOS Matrix ISFSI pad was designed to hold 64 dry shielded canisters (DSCs), each with 37 spent fuel assemblies. The EOS Matrix design contains two levels of HSM-MXs (horizontal storage module-matrix). Currently the licensee had constructed 11 HSM-MXs, each capable of receiving one DSC, on the southeast portion of the ISFSI pad. During the first loading campaign Wolf Creek Generating Station planned on loading five DSCs into the lower level of the EOS Matrix. Inspectors observed loading activities associated with the first DSC loaded to the ISFSI.

During the onsite inspection, the inspectors evaluated and observed the following activities:

Fuel selection and spent fuel placement into the DSC

Removal of the loaded DSC from the spent fuel pool to the canister processing area

Welding and non-destructive testing of the lid-to-shell welds of the DSC

Canister vacuum drying and pneumatic testing of the DSC

Welding, non-destructive testing, and helium leak testing of the top plate and vent/drain port covers

Lifting and down-ending transfer cask/DSC from the processing area to the heavy haul transport trailer

Transport from the spent fuel building to the ISFSI pad using the heavy haul transport trailer

Use of the matrix loading crane to insert the DSC from the transfer cask to a lower level HSM-MX storage module.

===60856 - Review of 10 CFR 72.212(b) Evaluations The inspection was conducted to determine if Wolf Creek Generating Station met the general license requirements of 10 CFR Part 72 before conducting operations to load their ISFSI.

Review of 10 CFR 72.212(b) Evaluations===

(1) Wolf Creek Generating Station had elected to become a 10 CFR Part 72 general licensee in accordance with 10 CFR 72.210. In previous inspections throughout 2020 and 2021, the licensee had completed all required pre-operational activities required by the Certificate of Compliance and NRC had finished reviewing the majority of the site's programs and evaluations associated with 10 CFR 72.212. During the inspection period (January 1st through January 26, 2022), the inspectors continued the inspection of Wolf Creek's programs, procedures, and calculations performed by the licensee to meet the requirements of 10 CFR Part 72. Specifically, the inspectors completed the review of:

The finalized 10 CFR 72.212 Report, Rev. 0

Hazards Analysis for ISFSI

INSPECTION RESULTS

Failure to Establish Fire Compensatory Measure During Maintenance Activities Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-01 Open/Closed

[P.3] -

Resolution 71111.05 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to implement the fire protection program procedure requirements. Specifically, the licensee failed to implement appropriate fire compensatory measures during planned maintenance activities that prevented a fire and halon boundary door from self-closing and latching due to ventilation airflow.

Description:

On January 18, 2022, the inspectors were performing walkdowns for scheduled train A Class 1E electrical equipment air conditioning system (SGK05A) maintenance activity to verify the licensee implemented their planned risk-management measures. Specifically, the licensee placed the train B Class 1E electrical equipment air conditioning system (SGK05B) in cross-training operation as required by Technical Specification 3.7.20, Class 1E Electrical Equipment Air-Conditioning (A/C) System, in order to use SGK05B to cool the safety-related ac and dc electrical equipment in both trains and was implemented in accordance with Procedure SYS GK-201, Mitigating Actions for Inoperable SGK05 Train, Rev. 3A. During this walkdown, the inspectors identified safety-related dc switchgear room 4 (Room 3404), the active door (Door 34041), was not automatically closing and latching due to the increased differential pressure caused by the infrequent ventilation lineup, and no breach permit authorization for the door, or the required fire compensatory measure were posted in the area. Door 34041 was credited as a fire door and halon system boundary as documented in Procedure WCRE-35, Boundary Matrix, Revision 8, and was required to self-close and latch to meet the halon boundary requirements. Therefore, the licensee was required to initiate a breach authorization permit and a fire compensatory measure of an hourly fire watch for a nonfunctional halon system in accordance with Procedures AP 10-103, Fire Protection Impairment Control, Revision 36, and AP 10-104, Breach Authorization, Revision 39.

Specifically, Procedures AP 10-103 and AP 10-104 required the following:

Procedure AP 10-103, Step 5.6.1, stated, All personnel shall maintain operability/functionality of all required barriers. Note: Fire doors with automatic closers that do not close and latch on their own require a breach authorization permit, which is also required by Procedure SYS GK-201 for any dc electrical switchgear room or battery room doors that do not close and latch automatically and initiate a condition report (CR) and occurs approximately 15 to 20 minutes after establishing the SGK05B cross-training alignment. The inspectors reviewed the previous occurrences of the implementation of Procedure SYS GK-201 and identified two CRs where dc electrical room and battery doors did not automatically close and latch. The doors identified where random and never the same. In response, the licensee developed a corrective action to install a second closure on multiple doors affected by the condition that prevented Door 34041 from automatically closing and latching. However, at the time inspectors identified Door 34041 was not automatically closing and latching, the second closure mechanism was not installed, and the inspectors did not identify an interim corrective action (i.e., establish an hourly fire watch when implementing Procedure SYS GK-201) until the final corrective action was completed.

Procedure AP 10-104, Step 5.5.1, stated, Fire protection [personnel] shall specify the compensatory measure required when a fire barrier is breached, degraded, or determined inoperable/nonfunctional.

Procedure AP 10-103, Attachment E, Required Action C.1, required the establishment of an hourly fire watch for any other halon system nonfunctional.

The inspectors informed the licensee of the condition of Door 34041. The licensee established the required hourly fire watch per barrier permit BAP 22-0015 and initiated CR 10011703.

Corrective Actions: The licensee established the required fire compensatory measure for an inoperable halon boundary door.

Corrective Action References: CR 10011703

Performance Assessment:

Performance Deficiency: The licensees failure to establish fire compensatory measures for a halon boundary door failure to automatically close and latch during air conditioning system SGK05A maintenance activities was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors 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 failure of Door 34041 self-closing mechanism to close and latch the door degraded the fire barrier function and prevented the door from retaining a halon release and required a fire compensatory measure of stationing an hourly fire watch for the halon protected safety-related switchgear room 4 during planned train A Class 1E air conditioning system maintenance activity.

Significance: The inspectors assessed the significance of the finding using Appendix F, Fire Protection and Post - Fire Safe Shutdown SDP. The inspectors assigned the finding a fire Category 1.4.1 using Inspection Manual Chapter 0609, Appendix F, Attachment 1, Fire Protection Significance Determination Process Worksheet, dated May 2, 2018, because the finding involved fire prevention and administrative controls. The inspectors determined that the finding had very low safety significance (Green) because the finding:

(1) did not increase the likelihood of a fire, delay detection of a fire, or resulted in a more significant fire than previously analyzed such that credited safe shutdown strategy could be adversely impacted; and
(2) the degraded fire confinement element continued to provide adequate fire endurance to prevent fire propagation through the fire confinement element given the combustible loading and location of equipment important to safe shutdown in the fire area of concern.

Specifically, there was no combustible material or safety equipment that constituted a fire target in the hallway adjoining the degraded door.

Cross-Cutting Aspect: P.3 - Resolution: The organization takes effective corrective actions to address issues in a timely manner commensurate with their safety significance.

Specifically, the licensee failed to establish interim corrective actions to ensure fire compensatory measures were established for inoperable halon boundary doors during air conditioning system SKG05A maintenance activities until the final corrective action was completed.

Enforcement:

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

The licensee established Procedures AP 10-103, Revision 36, and AP 10-104, Revision 39, for impairments of the fire protection system and instructions to maintain required barriers for fire protection.

Procedure AP 10-104, Step 5.5.1, stated, Fire protection [personnel] shall specify the compensatory measure required when a fire barrier is breached, degraded, or determined inoperable/nonfunctional.

Procedure AP 10-103, Attachment E, Required Action C.1, required the establishment of an hourly fire watch patrol for any other halon system nonfunctional.

Contrary to the above, on January 18, 2022, the licensee failed to implement fire protection program Procedures AP 10-104 and AP 10-103 to specify compensatory measures when a fire barrier was degraded and to establish hourly fire watch patrols with a nonfunctional halon system. Specifically, when Door 34041 self-closing mechanism failed to close and latch the door when it was opened with SGK05B in cross-train mode, the fire barrier was degraded but the licensee failed to establish the hourly fire watch patrol for the halon system being nonfunctional.

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

Failure to Correct Inadequate Procedural Guidance Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-02 Open/Closed

[P.5] -

Operating Experience 71111.12 The inspectors reviewed a self-revealed Green finding and associated non-cited violation of Technical Specification 5.4.1.a, for the licensees failure to properly pre-plan and perform maintenance that can affect the performance of safety-related equipment. Specifically, the licensee failed to correct inadequate procedural guidance associated with filling and venting the emergency diesel generator jacket water and intercooler system following planned maintenance. This condition resulted in air binding the emergency diesel generator A jacket water keep warm pump, resulting in jacket water leakage greater than allowed to support emergency diesel generator operability.

Description:

On January 10, 2022, following the performance of emergency diesel generator (EDG) A monthly operability run, a jacket water leak was identified from jacket water keep warm pump PKJ01A at 25 milliliters per minute (mL/min). This leak rate was in excess of the maximum allowed jacket water leak operability limit of 8.6 mL/min to support a 7-day mission time for EDG A. The licensee declared EDG A inoperable, isolated the jacket water leak from pump PKJ01A to restore operability of EDG A, replaced pump PKJ01A and returned it to service, and performed a dynamic vent of the jacket water system in addition to performing the static fill and vent in accordance with Procedure SYS KJ-130, Removal and Restoration of EDG Support Systems, Revision 13. The licensee entered this condition into corrective action program as CR10011538 and performed an equipment performance evaluation.

The inspectors reviewed the equipment performance evaluation documented in CR 10011539, previous corrective actions documented in CR 137247 due to EDG A jacket water low temperature and pressure alarms during a maintenance run, and internal and external EDG operating experience. From these reviews the inspectors noted the following:

CR 10011539: The most probable cause of the jacket water leak from PKJ01A mechanical seal was due to running the pump air bound following maintenance performed in September 2021 in accordance with Work Order 19-4564130-000. This most likely occurred when placing pump PKJ01A and jacket water heaters into service without adequately filling and venting the jacket water system in accordance with Procedure SYS KJ-130. With pump PKJ01A air bound, overheating occurred causing the shaft to slip on the inner race of the pump bearing and damaging the seal surface due to movement. This seal surface damage increased until the jacket water leak occurred on January 10, 2022, causing EDG A to be declared inoperable until the leak was isolated and repaired.

CR 137247: On October 15, 2019, the low jacket water pressure and low temperature alarm was received approximately 10 minutes into the EDG A maintenance run, which resulted in elevated EDG A operating temperatures. Additional venting of EDG A jacket water system resulted in unexpected amounts of air being vented from the system. The licensee determined that the system had likely been air bound, and that the jacket water low pressure was due to air binding of the engine driven jacket water pump. Lastly, the temperature of the jacket water indication showing a stable reading around 115 degrees Fahrenheit was because there was no/flow through the system.

This explained why no temperature alarms were received until after EDG A was secured, which resulted in movement of the air voids, and subsequent change in the temperature readings. The licensee determined the fill and vent guidance contained in Procedure SYS KJ-130 was inadequate, but the licensee only considered it an enhancement due to installing additional high point vents on the EDGs engine driven jacket water and intercooler system.

External Operating Experience: The inspectors identified the following operation experience from May 4, 2020, which was not identified by the licensee and evaluated for similar impacts filling and venting EDG jacket water and intercooler systems following maintenance activities. An EDG at another operating reactor station tripped on low intercooler pressure due to air entrained in the system after maintenance and post-maintenance testing was performed. The EDG system was not fully vented because guidance in the venting procedures lacked instructions to perform a robust dynamic venting following draining of the air coolant and jacket water cooling systems.

The venting procedures used were consistent with current industry standards and written vendor guidance, but not sufficient to address the specific circumstance encountered in this event. The inadequate system venting occurred due to EDG jacket water and air coolant systems containing many small, localized high points.

Also, low temperature coolant has more oxygen entrained in it and will release oxygen into the coolant system when it is heated up during full speed and full operation.

Passive venting of the system can remove most of the air. However, to be effective, a more robust venting process was necessary to dynamically vent at multiple points in the system during heat up and while running loaded to ensure all air was removed and ensure the air coolant cooler did not retain trapped air, it was important to validate the temperature control valve (provides flow through the air coolant cooler) was open when venting.

The inspectors reviewed the above information and determined the licensee failed to use external operating experience to develop corrective actions ensure adequate filling and venting guidance was contained in Procedure SYS KJ-130. Specifically, the licensee did not incorporate the use of dynamic venting when the jacket water and intercooler system was partial drained to ensure all air voids are removed from the system.

Corrective Actions: Incorporated dynamic venting guidance for when the EDG jacket water and intercooler system was partially drained for maintenance activities are contained in Procedure SYS KJ-130.

Corrective Action References: CR 10011538

Performance Assessment:

Performance Deficiency: The licensees failure to correct inadequate procedural guidance associated with filling and venting the EDG jacket water and intercooler system following maintenance 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, the failure to adequately fill and vent the EDG jacket water and intercooler system following EDG A jacket water keep warm pump maintenance resulting in air bending the pump and jacket water leakage greater than allowable to maintain EDG operability.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Screening Questions, the finding was determined to be very low safety significance (Green) because it:

(1) was not a design deficiency,
(2) did not represent a loss of system and/or function,
(3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,
(4) did not represent a loss of probabilistic assessment (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) did not represent a loss of a PRA system and/or function 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) did not result in the loss of high safety-significant, nontechnical specification train.

Cross-Cutting Aspect: P.5 - Operating Experience: The organization systematically and effectively collects, evaluates, and implements relevant internal and external operating experience in a timely manner. Specifically, the licensee failed to collect, evaluate, and implement industry operating experience associated with filling and venting EDG jacket water/intercooler system following maintenance.

Enforcement:

Violation: Technical Specification 5.4.1.a, requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Quality Assurance Program Requirements, Revision 2, February 1978. Regulatory Guide 1.33, Appendix A, Section 9, Procedures for Performing Maintenance, requires, in part, that maintenance should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. The licensee established Procedure SYS KJ-130, Revision 13, to fill and vent the EDG jacket water and intercooler system.

Contrary to the above, from February 19, 2020 to February 10, 2022, the licensee failed to maintain written procedures, documented instructions, or drawings appropriate to the circumstances to filling and venting the EDG jacket water and intercooler system.

Specifically, the licensee failed to correct inadequate procedural guidance associated with filling and venting the EDG jacket water and intercooler system in accordance with Procedure SYS KJ-130. This condition resulted in air binding the EDG A jacket water keep warm pump and damaging the pump seal that resulted in jacket water leakage greater than allowed to support EDG operability.

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

Failure to Schedule Preventive Maintenance to Prevent Unacceptable Preconditioning Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2022001-03 Open/Closed None (NPP)71111.22 The inspectors identified a Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations, Part 50 (10 CFR Part 50), Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensee failure to accomplish instructions, procedures, or drawings appropriate to the circumstances that would have prevented unacceptable preconditioning of the 125 Vdc battery chargers. Specifically, the licensee failed to accomplish Procedure AI 29B-003, Guidance to Prevent Unacceptable Preconditioning Prior to Testing, Revision 2, to not schedule preventive maintenance prior to conducting as-found 125 Vdc battery charger technical specification surveillance testing.

This resulted in three examples of unacceptable preconditioning the 125 Vdc battery chargers.

Description:

The inspectors reviewed previously performed 18-month 125 Vdc battery charger operational surveillance tests that were performed in accordance with (IAW)

Procedure STS MT-020, 125 Volt DC Battery Charger Operational Test, Revision 26B, to verify the requirements of Surveillance Requirement 3.8.4.6 were met. Specifically, the 125 Vdc battery chargers supplied greater than or equal to 300 amps at greater than or equal to 128.4 V for greater than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. During this review, the inspectors identified the licensee was performing 125 Vdc battery charger preventive maintenance (PM) IAW Procedure MPE E051Q-01, Semi-Annual Cleaning and Testing of Internal Components in Battery Chargers, Revision 20, prior to performing the 125 Vdc battery charger as-found technical specifications surveillance testing. Additionally, the inspector identified three work orders that disturbed the as-found condition of the 125 Vdc battery chargers prior to performing Procedure STS MT-020 and determined it was unacceptable preconditioning IAW NRC Inspection Manual Part 9900 Technical Guidance, Maintenance - Preconditioning of Structures, Systems, and Components (SSC) before Determining Operability, and licensee Procedure AI 29B-003, Revision 2. Specifically, the inspectors identified the following during their inspection activities:

Inspection Manual Part 9900 Technical Guidance defines unacceptable preconditioning as; The alteration, variation, manipulation, or adjustment of the physical condition of the SSC [structures, systems, and components] before or during technical specification surveillance testing that will alter one or more of the SSCs operational parameters which results in acceptable test results. Such changes could mask the actual as-found condition of the SSC and possibly result in an inability to verify the operability of the SSC. In addition, unacceptable preconditioning could make it difficult to determine whether the SSC would perform its intended function during an event in which the SSC might be needed. The specific example of unacceptable preconditioning for electrical equipment was Inspectors noted that electrical loads were removed from a number of 480 V circuit breakers before surveillance testing was performed. In addition, surveillance procedures instructed technicians to inspect, clean, and lubricate several breakers before performing as-found testing. This example is similar to what occurred in Work Orders 18-441067-000, 18-444596-000, and 19-452686-000.

Work Order 18-441067-000: The licensee replaced current and sensing card for train A 125 Vdc distribution system battery charger prior to performing as-found surveillance testing.

Work Order 18-444596-000: The licensee replaced electrocyte capacitors for train A 125 Vdc distribution system battery charger NK021 prior to performing as-found surveillance testing.

Work Order 19-452686-000: The licensee replaced electrocyte capacitors for train B 125 Vdc distribution system battery charger prior to performing as-found surveillance testing.

In each case, the equipment replaced within the 125 Vdc battery chargers impacted the ability to verify as-found operability of the battery chargers. Each component was replaced due to visible damage on the component, such as scorch marks and dents.

Procedure AI 29B-003 has the following statements:

o Step 6.3.1 states in part, that Initiative to integrate maintenance and surveillance testing may inadvertently introduce unrecognized equipment preconditioning. The practice of scheduling a routine surveillance test to follow a maintenance activity so that test can satisfy the periodic surveillance requirement as well as serve as the post-maintenance test could result in unacceptable preconditioning.

Example: Following maintenance, the baseline performance or condition data must be recorded if a post-maintenance test is used as the operability test of record. The baseline data are necessary to compare to future test data to determine equipment conditions that develop over time. However, in some circumstance recording post-maintenance baseline data in lieu of recording the as-found data could prevent detection of equipment performance problems.

o Step 6.4.1, states in part, that Except where there is a need to protect personnel or prevent equipment damage, preventive maintenance should not be routinely performed before surveillance testing.

From the above information, the inspectors determined there was not a need to perform PMs prior to as-found technical specification surveillance testing to protect personnel or prevent equipment damage, therefore scheduling PMs IAW Procedure MPE E051Q-01 prior to performing as-found technical specification surveillance testing IAW Procedure STS MT-020 was unacceptable preconditioning of the 125 Vdc battery chargers. The inspectors informed the licensee of their concern of unacceptable preconditioning of 125 Vdc battery chargers and they initiated CR 10011968.

Corrective Actions: The licensee performed as-found technical specification testing of train A 125 Vdc distribution system battery charger NK023 prior to perform PMs IAW Procedure MPE E051Q-01.

Corrective Action References: CR 10011968

Performance Assessment:

Performance Deficiency: The licensees failure to schedule PMs to prevent unacceptable preconditioning of 125 Vdc battery chargers prior to technical specification surveillance testing was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human 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, the licensee scheduled PMs prior to performing as-found 125 Vdc battery charger technical specification required surveillance testing, which resulted in three examples of unacceptable preconditioning and the inability to verify operability of the 125 Vdc battery chargers.

Significance: The inspectors assessed the significance of the finding using 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 design deficiency,
(2) did not represent a loss of system and/or function,
(3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,
(4) did not represent a loss of the probability risk analysis 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) did not represent a loss of probability risk analysis system and/or function 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) did not result in the loss of a high safety-significant, nontechnical specification train.

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. The licensee established Procedure AI 29B-003 as the implementing procedure to prevent unacceptable preconditioning due to performing PM prior surveillance testing in accordance with Step 6.4.1, which states in part, that Except where there is a need to protect personnel or prevent equipment damage, PM should not be routinely performed before surveillance testing..

Contrary to the above, prior to February 7, 2022, the licensee failed to ensure that an activity affecting quality was accomplished in accordance with documented instructions, procedures, or drawings. Specifically, the licensed failed to accomplish Procedure AI 29B-003, Step 6.4.1 when scheduling 125 Vdc battery charge PM prior to performing as-found technical specification surveillance testing. During three previous maintenance activities, components within the 125 Vdc system were replaced prior to taking as-found amperage and voltage surveillance readings to ensure that the system was operable prior to conducting maintenance, with no need to protect personnel or prevent equipment damage.

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 January 26, 2022, the inspectors presented the ISFSI first loading inspection and Part 72.212 programs inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.

On March 10, 2022, the inspectors presented the triennial heat exchanger and heat sink performance inspection results to Mr. C. Reasoner, Chief Executive Officer and Chief Nuclear Officer, and other members of the licensee staff.

On April 7, 2022, the inspectors presented the integrated inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

60855

Corrective Action

Documents

CR 10011762

NDE Chemical Batch Numbers

Rev 0

60855

Corrective Action

Documents

Resulting from

Inspection

CR 10011697

ISFSI First Loading Inspection NRC Identified Condition

Rev 0

60855

Engineering

Evaluations

2.48 CP 20163

Fire Hazard Review for fuel transfer activities

Rev 0

60855

Procedures

AI 19F-001

WCNOC ISFSI Campaign Oversight Procedure

Rev 1

60855

Procedures

PTIP 30501-

5.11c

EOS 37PTH TC Handling and Fuel Loading

Rev 3

60855

Procedures

PTIP 30501-

5.11d

EOS 37PTH DSC Drying, Backfilling, and Sealing

Rev 3

60855

Procedures

PTIP 30501-

5.11e

DSC Insertion into HSM-MX

Rev 5

60855

Procedures

PTIP 30501-

5.11g

Guidance for ISFSI Equipment Malfunctions

Rev 1

60856

Engineering

Evaluations

CFR 72.212

Evaluation Report

WCGS Dry Fuel Storage System for Spent Nuclear Fuel

Docket Number 72-1042

Rev 0

60856

Engineering

Evaluations

HG-X-001

WCGS Hazards Evaluation for ISFSI

Rev 1

71111.01

Calculations

GK-M-007

Battery Rooms, Switchboard Rooms, Switchgear Room

Temperature During Winter Concurrent with Station Blackout

Conditions

71111.01

Corrective Action

Documents

Condition Reports

109974, 10011521, 10011845,

71111.01

Drawings

M-12GK02

Piping and Instrumentation Diagram Control Building HVAC

71111.01

Drawings

M-12GK03

Piping and Instrumentation Diagram Control Building HVAC

71111.01

Procedures

CKL ZL-009

Site Reading Sheets

21

71111.01

Procedures

INC C-1001

Calibration of Switches

71111.01

Procedures

STS MT-018

Weekly Inspection of 125 VDC Lead-Calcium Batteries

23B

71111.01

Procedures

SYS OPS-008

Cold Weather Operations

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Work Orders

WO

20-463180-000, 22-477245-000

71111.04

Calculations

NK-E-001

25 VDC Class 1E Battery System Sizing, Voltage Drop and

Short Circuit Studies

71111.04

Calculations

NK-E-004

25 VDC Class 1E Battery Charger Sizing

71111.04

Corrective Action

Documents

Condition Reports

2915, 136319, 136755, 137903, 141961, 142198,

10000839, 10004515, 10006574

71111.04

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10011571, 10011703, 10012246, 10012261

71111.04

Drawings

E-11010

DC Main Single Line Diagram

71111.04

Drawings

E-11013

Installation, Inspection and Testing Details for Electrical

Equipment and Cables

71111.04

Drawings

E-11NK01

Class 1E 125 V DC System Meter and Relay Diagram

71111.04

Drawings

KD-7496

One Line Diagram

71111.04

Drawings

M-12EJ01

Piping and Instrumentation Diagram Standby Residual Heat

Removal System

71111.04

Drawings

M-12EN01

Piping and Instrumentation Diagram Standby Containment

Spray System

71111.04

Drawings

M-12KJ01

Piping and Instrumentation Diagram Standby Diesel

Generator A Cooling Water System

71111.04

Drawings

M-12KJ03

Piping and Instrument Diagram Standby Diesel Generator

A Lube Oil System

71111.04

Engineering

Changes

CCP 08052

KKJ01A/B Lube Oil/Jacket Water Alarm Setpoints

71111.04

Miscellaneous

261B

Instruction Manual for 3 Phase, Thyristor Controlled, Class

1E 130V Battery Charger NK21, NK23, NK24, NK25

2/05/1979

71111.04

Miscellaneous

E-051-00090

Instruction Manual for 3 Phase, Thyristor Controller, Class

1E, 130V Battery Charger NK21, NK22, NK24, NK25

W11

71111.04

Miscellaneous

E-10NK

System Description for 125-Volt DC System

71111.04

Miscellaneous

E-1F9915

Design Basis Document for OFN RP-017, Control Room

Evacuation

71111.04

Miscellaneous

M-018-00309

Instruction Manual for Emergency Diesel Generator System

W141

71111.04

Procedures

ALR 00-020D

DG NE01 Trouble

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Procedures

ALR 00-025B

NN11 Inv Trbl/XFR

10A

71111.04

Procedures

ALR 00-025C

NK01 Trouble

13A

71111.04

Procedures

ALR 301

25 VDC Class 1E Switchboard NK01

71111.04

Procedures

ALR 501

Standby Diesel Engine System Control Panel KJ-121

71111.04

Procedures

ALR 502

Standby Diesel Engine System Control Panel KJ-122

71111.04

Procedures

AP 21D-006

Safety Function Determination Program

71111.04

Procedures

BD-EMG C-0

Loss of All AC Power

71111.04

Procedures

CKL EJ-120

RHR System Lineup

71111.04

Procedures

CKL EN-120

Containment Spray System Lineup

15A

71111.04

Procedures

CKL NK-131

NK Distribution Switchboard Switch Lineup Checklist

71111.04

Procedures

EMG C-0

Loss of All AC Power

71111.04

Procedures

MGE TL-001

Wiring Termination and Lug/Connector Installation

26B

71111.04

Procedures

OFN NK-020

Loss of Vital 125 VDC Bus NK01 NK02 NK03 and NK04

71111.04

Procedures

OFN RP-013

Control Room Not Habitable

71111.04

Procedures

OFN RP-017

Control Room Evacuation

71111.04

Procedures

SYS GK-201

Mitigating Actions for Inoperable SGK05 Train

3A

71111.04

Procedures

SYS KJ-123

Post Maintenance Run of Emergency Diesel Generator A

71111.04

Procedures

SYS KJ-130

Removal and Restoration of EDG Support Systems

71111.04

Procedures

SYS NK-131

Energizing NK Buses

71111.04

Work Orders

WO

19-450375-000, 19-454090-000, 19-454090-004, 19-

454090-006, 20-465779-000, 21-469855-000

71111.05

Corrective Action

Documents

Condition Reports

0011703, 10000274, 10000500, 10000916, 10003704,

10009970

71111.05

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10011727, 10011967, 10012462

71111.05

Drawings

M-12KC02

Piping and Instrumentation Diagram Fire Protection System

71111.05

Engineering

Changes

DCP 020553

Tandem Door Closer Allowance

71111.05

Miscellaneous

BAG-22-0015

Breach Authorization Permit

71111.05

Miscellaneous

BAP-21-0268

Breach Authorization Permit

71111.05

Miscellaneous

E-1F9905

Fire Hazard Analysis

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.05

Miscellaneous

E-1F9910

Post-Fire Safe Shutdown Area Analysis

71111.05

Miscellaneous

M-663-00017

Wolf Creek Nuclear Operating Corporation Penetration Seal

Typical Details

W22

71111.05

Miscellaneous

WCRE-35

Boundary Matrix

71111.05

Procedures

AP 10-103

Fire Protection Impairment Control

71111.05

Procedures

AP 10-106

Fire Preplans

71111.05

Procedures

AP 10-106

Fire Preplans

71111.05

Procedures

AP 22C-003

On-Line Nuclear Safety and Generation Risk Assessment

71111.05

Procedures

CNT-MC-905

Dow Corning 3-6548 Silicone RTV Foam Seals and

Elastomer Top Cap

71111.05

Procedures

STN FP-450

Fire Damper Inspection and Drop Test

71111.05

Procedures

SYS GK-201

Mitigating Actions for Inoperable SGK05 Train

3A

71111.05

Work Orders

WO

2-357145-064, 20-467509-059, 20-467509-060,

21-470940-088

71111.06

Calculations

FL-03

Flooding of Individual Auxiliary Building Rooms

71111.06

Calculations

FL-07

Flooding of Auxiliary Bldg. Rooms - Elevation 2047 ft - 6 in

71111.06

Corrective Action

Documents

Condition Reports

118663, 140064, 10010906

71111.06

Drawings

M-12EG01

Piping and Instrumentation Diagram Component Cooling

Water System

71111.06

Miscellaneous

BAP-22-0057

Breach Authorization Permit

71111.06

Miscellaneous

BAP-22-0058

Breach Authorization Permit

71111.06

Miscellaneous

WCRE-03

Wolf Creek Tank Document

71111.06

Miscellaneous

WCRE-35

Boundary Matrix

71111.06

Procedures

ALR 00-008B

Serv WTR Press Hi LO

71111.06

Procedures

ALR 00-053D

CCW SRG TK B Lev HILO

71111.06

Procedures

ALR 00-054B

CCW PMP B/D Press Lo

71111.06

Procedures

ALR 00-055A

ESW PMP A Press LO

11A

71111.06

Procedures

AP 10-106

Fire Preplans

71111.06

Procedures

OFN EG-004

CW System Malfunctions

71111.06

Procedures

OFN SG-003

Natural Events

71111.06

Procedures

TMP 22-002

B CCW Heat Exchanger Flush

71111.06

Work Orders

WO

16-418172-000, 22-477605-000

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.07A

Calculations

GK-M-008

SGK04A/B and SGK05A/B Operation with 15% Tubes

Plugged

71111.07A

Calculations

GK-M-009

Tube Plugging Criteria for Control Room A/C Unit SGK04A/B

Condensers and ESF Switchgear Rooms A/C Units

SGK05A/B Condensers

71111.07A

Calculations

GK-M-015

Cooling and Heating Load for Control Building Class 1E

Electrical Equipment Areas during Accident Conditions -

Train B

0, CNN6,

CNN7

71111.07A

Calculations

GK-M-016

Wolf Creek Control Building Loss of Class 1E A/C Gothic

Room Heat Up Analysis with Installed Crosstie Fans and

Louvers

71111.07A

Corrective Action

Documents

Condition Reports

10010853, 10011274, 10011920, 10011933, 10011935,

10012140

71111.07A

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10011996

71111.07A

Drawings

M-12GK03

Piping and Instrumentation Diagram Control Building HVAC

71111.07A

Miscellaneous

M-622.1A-0089

Instruction Manual for SGK04A, SGK04B, SGK05A, and

SGK05B Air Conditioning Condensers

W18

71111.07A

Procedures

AP 23L-002

Heat Exchanger Program

71111.07A

Procedures

STN PE-037B

ESW Train B Heat Exchanger Flow and DP Trending

71111.07A

Work Orders

WO

20-457635-000, 20-464226-000, 20-467458-000,

21-469292-000

71111.07T

Calculations

EF-M-029

Minimum ESW Temperature Rise

71111.07T

Calculations

GK-M-009

Tube Plugging Criteria for Control Room A/C Unit SGK04A/B

Condensers and ESW Switchgear Rooms A/C Unit

SGK05A/B Condensers

71111.07T

Calculations

GK-M-010

Tube Pitting Criteria for Control Room SGK04A/B and

Electrical Switch Gear Rooms SGK05A/B Condensing Units

71111.07T

Calculations

KJ-M-015

EKJ06A/B Thermal Performance Calculation

71111.07T

Corrective Action

Documents

Condition Reports

10011987, 10011857, 10010853, 14513, 108013, 122602,

141615, 14513

71111.07T

Drawings

C-K278

Essential Service Water Buried Pipe Replacement Project

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Plan and Sections - Discharge Marine Work

71111.07T

Drawings

M-1HX001

Heat Exchanger Tube Sheet Maps

71111.07T

Drawings

S-0080

Ultimate Heat Sink Plan and Sections

71111.07T

Drawings

S-0081

Ultimate Heat Sink Dam Plan, Profile and Section

G

71111.07T

Drawings

S-0184

ESWS Pumphouse Plan and Sections

K

71111.07T

Miscellaneous

Final Report June 2021 Hydrographic Survey

09/18/2019

71111.07T

Miscellaneous

Strategic Lake Water Chemistry Plan

71111.07T

Miscellaneous

AP 29D-001

UHS Monitoring Plan

71111.07T

Miscellaneous

C-302

Specification for Suction Dredging the Ultimate Heat Sink

71111.07T

Miscellaneous

C-404

Periodic Surveillance of Safety Related Water Control

Structures and Reservoir

71111.07T

Miscellaneous

M-018E

Design Specification for Replacement Jacket Water Heat

Exchangers

71111.07T

Miscellaneous

M-620B-00003

Coil Performance Topical Report AL-6XN Tube Coil Design

W03

71111.07T

Miscellaneous

M-622.1A-VDS-

1.07

SGK05A/B Condenser Vendor Data Sheet

71111.07T

Procedures

AI 07A-008

Lake Water Chemical Treatment Program

71111.07T

Procedures

AP 23L-001

Lake Water Systems Corrosion and Fouling Mitigation

Program

71111.07T

Procedures

AP 23L-002

Heat Exchanger Program

71111.07T

Procedures

QCP-20-514

Eddy Current Testing

71111.07T

Procedures

QCP-20-518

Visual Examination of Heat Exchangers and Piping

Components

71111.07T

Procedures

STN EF-022B

ESW Train B Post-LOCA Flow Balance

2A

71111.07T

Procedures

STN MT-004

Ultimate Heat Sink Dam Surveillance Vertical Movement

71111.07T

Procedures

STN MT-005

Ultimate Heat Sink Reservoir and ESW Intake Channel

Sedimentation Surveillance

71111.07T

Procedures

STN PE-037A

ESW Train A Heat Exchanger Flow and DP Trending

71111.07T

Procedures

STN PE-037B

ESW Train B Heat Exchanger Flow and DP Trending

71111.07T

Procedures

STN PE-038

Containment Cooler Performance Test

71111.07T

Procedures

STS ME-075

SGK05B Heat Exchanger Inspection

71111.07T

Procedures

SYS CI-010B

B Train ESW Chemical Addition

71111.07T

Procedures

SYS EF-300B

ESW/Service Water Macrofoul Treatment for Train B

0A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.07T

Work Orders

WO

17-432437-006, 20-467458-000, 19-451425-000,

21-472154-000, 19-457078-005, 20-457635-000,

19-452027-000, 20-458079-000, 21-469292-001,

20-460518-001, 20-460518-000, 19-452880-001,

20-459739-000, 15-399213-011, 15-399213-001,

18-438972-001, 20-459054-000, 18-444695-000,

20-462555-000

71111.11Q

Procedures

ALR 00-058B

VCT VLV Not in VCT Pos

71111.11Q

Procedures

ALR 00-065F

OSA No. 1

71111.11Q

Procedures

OFN NK-020

Loss of Vital 125 VDC Bus NK01 NK02 NK03 and NK04

71111.12

Calculations

AN-99-031

Development of PSA Based Reliability Performance Criteria

for Maintenance Rule

71111.12

Corrective Action

Documents

Condition Reports

64598, 137247, 137903, 141515, 141532, 10009039,

10009046, 10010001, 10010040, 10010305, 10010812,

10010851, 10010870, 10010599, 10011759, 10011538,

10011591, 10011639, 10011645, 10011655, 10011885,

10012090, 10012477

71111.12

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10012147, 10012220, 10012237, 10012289, 10012304,

10012377, 10012398, 10012448, 10012449, 10012475,

10012584, 10012596

71111.12

Drawings

M-12KJ01

Piping and Instrumentation Diagram Standby Diesel

Generator A Cooling Water System

71111.12

Drawings

M-13KJ03

Small Piping Isometric Standby Diesel System Lube Oil and

Jacket Water

71111.12

Engineering

Changes

CP 014566

SGK05A&B PMT-Bitzer Compressor Replacement

71111.12

Miscellaneous

E-050A-00011

Lucent Technologies Lineage 2000 Round Cell Battery

W03

71111.12

Miscellaneous

M-018-00309

Instruction Manual for Emergency Diesel Generator System

W141

71111.12

Miscellaneous

M-622.1A-00059

Qualification for 2.5 Condenser Water Regulating Valve

W02

71111.12

Procedures

AP 23M-001

WCGS Maintenance Rule Program

71111.12

Procedures

AP 24G-001

Dedication of Commercial Grade Items

9A

71111.12

Procedures

EDI 23M-050

Equipment Evaluation for Maintenance Rule

71111.12

Procedures

MGE EOOP-11

Molded Case Circuit Breaker and Ground Fault Sensor

37A

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Testing

71111.12

Procedures

STS MT-018

Weekly Inspection of 125 VDC Lead-Calcium Batteries

23A

71111.12

Procedures

SYS KJ-130

Removal and Restoration of EDG Support Systems

71111.12

Procedures

SYS OQT-001A

Operations A Train Quarterly Tasks

71111.12

Work Orders

WO

17-423314-000, 17-423314-005, 17-423314-000,

19-450375-000, 19-455845-000, 19-456413-000,

20-465535-000

71111.13

Corrective Action

Documents

Condition Reports

10011538, 10011756, 10012045,10012261

71111.13

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10011604, 10011605, 10011724, 10011805

71111.13

Drawings

KD-7496

One Line Diagram

71111.13

Drawings

M-12BN01

Piping & Instrumentation Diagram Borated Refueling Water

Storage System

71111.13

Drawings

M-12KJ01

Piping and Instrumentation Diagram Standby Diesel

Generator A Cooling Water System

71111.13

Engineering

Changes

CCP 08052

KKJ01A/B Lube Oil/Jacket Water Alarm Setpoints

71111.13

Miscellaneous

M-018-00309

Instruction Manual for Emergency Diesel Generator System

W141

71111.13

Procedures

AI 22C-013

Protected Equipment Program

23A

71111.13

Procedures

AP 21C-001

Wolf Creek Substation

71111.13

Procedures

AP 21D-006

Safety Function Determination Program

71111.13

Procedures

AP 22C-003

On-Line Nuclear Safety and Generation Risk Assessment

71111.13

Procedures

AP 22C-007

Risk Management and Contingency Planning

71111.13

Procedures

AP 22C-008

Qualitative Risk Management

5A

71111.13

Procedures

EMG E-0

Reactor Trip or Safety Injection

71111.13

Procedures

EMG ES-02

Reactor Trip Response

71111.13

Procedures

OFN AF-025

Unit Limitations

71111.13

Procedures

OFN KJ-032

Local Emergency Diesel Startup

71111.13

Procedures

OFN NB-030

Loss of AC Emergency Bus NB01 (NB02)

39A

71111.13

Procedures

OFN RP-017

Control Room Evacuation

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.13

Procedures

STS NB-005

Breaker Alignment Verification

71111.13

Procedures

SYS KU-122

Energizing NB02 from Station Blackout Diesel Generators

71111.13

Procedures

SYS SY-120

Sharpe Diesel Operation and Alignment to Site

14B

71111.13

Work Orders

WO

21-474284-001, 22-476871-000, 22-477088-000,

2-477167-000

71111.15

Calculations

EG-09-W

Tube Plugging for CCW Heat Exchangers EEG01A/B Max.

CCW Temperature-LOCA

0, CN002,

CN004

71111.15

Calculations

EG-M-032

Component Cooling Water Heat Exchanger Performance

During Normal Operations, Shutdown at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />),

and Post-LOCA Recirculation

71111.15

Calculations

GK-M-009

Tube Plugging Criteria for Control Room A/C Unit SGK04A/B

Condensers and ESF Switchgear Rooms A/C Unit

SGK05A/B Condensers

71111.15

Corrective Action

Documents

Condition Reports

10008827, 10008829, 10009004, 10010853, 10011274,

10011538, 10011562, 10011724, 10011770, 10011825,

10012045, 10012402, 10012403, 10012432, 10012488,

10012624

71111.15

Drawings

M-12AL01

Piping and Instrumentation Diagram Auxiliary Feedwater

System

71111.15

Drawings

M-12EF01

Piping Instrumentation Diagram Essential SVC Water

System

71111.15

Drawings

M-12EF02

Piping Instrumentation Diagram Essential Service Water

System

71111.15

Drawings

M-12GK03

Piping and instrumentation Diagram Control Building HVAC

71111.15

Drawings

M-1HX001

Heat Exchanger Tube Sheet Maps

71111.15

Drawings

M-1HX001, Sheet

Heat Exchanger Tube Sheet Map Component Cooling Water

Heat Exchanger B (South End) EE01B

71111.15

Drawings

S8N26-13

Schematic +48, +15 and +/- 15 VDC Power Supplies

D

71111.15

Engineering

Changes

CCP 08052

KKJ01A/B Lube Oil/Jacket Water Alarm Setpoints

71111.15

Miscellaneous

M-018-00309

Instruction Manual for Emergency Diesel Generator System

W141

71111.15

Miscellaneous

WCRE-34

Fourth 10-Year Interval Inservice Testing Basis Document

71111.15

Operability

Evaluations

EF-22-001

Essential Service Water System and Component Cooling

Water Heat Exchanger B

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Procedures

ALR 00-059D

CPIS

2A

71111.15

Procedures

ALR 00-127C

AFW Suct Switch to ESW

8B

71111.15

Procedures

ALR 00-129B

MD AFP Start

71111.15

Procedures

AP 21D-006

Safety Function Determination Program

71111.15

Procedures

AP 26C-004

Operability Determination and Functionality Assessment

45A

71111.15

Procedures

CKL AL-120

Auxiliary Feedwater Normal Lineup

44A

71111.15

Procedures

INC C-0063

ESFAS Cabinets SA036C, SA036D and SA036E Power

Down/Power Up

5B

71111.15

Procedures

QCP-20-518

Visual Examination of Heat Exchanger and Piping

Components

71111.15

Procedures

STN PE-037B

ESW Train B Heat Exchanger Flow and DP Trending

71111.15

Procedures

STS AL-103

TDAFW Pump Inservice Pump Test

71111.15

Procedures

STS AL-210C

TDAFW Inservice Check Valve Test

71111.15

Procedures

STS CR-004

Shift Log for Additional Monitoring

1A

71111.15

Procedures

STS IC-260

Channel Operational Test Auxiliary Feedwater Pump Suction

Pressure Low Transfer to ESW

71111.15

Procedures

STS PE-009

Control Room Ventilation System Flow Rate and Combined

Pressure Drop Test

71111.15

Procedures

SYS KJ-123

Post Maintenance Run of Emergency Diesel Generator A

71111.15

Procedures

SYS KJ-130

Removal and Restoration of EDG Support Systems

71111.15

Procedures

SYS NB-201

Transferring NB01 Power Sources

71111.15

Work Orders

WO

20-460826-000, 21-460039-000, 21-469040-000,

21-46992-001, 21-474963-002, 21-474963-003,

2-477088-000, 22-477167-000, 22-477433-000

71111.18

Corrective Action

Documents

Condition Reports

10012262, 10012521

71111.18

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10012606

71111.18

Drawings

M-12EG02

Piping and Instrumentation Diagram Component Cooling

Water System

71111.18

Procedures

TMP 22-002

B CCW Heat Exchanger Flush

71111.19

Corrective Action

Condition Reports

10011538, 10011717, 10011748

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

71111.19

Corrective Action

Documents

Resulting from

Inspection

Condition Report

10012471

71111.19

Drawings

E-13GK03A

Schematic Diagram Fire Isolation Damper

71111.19

Drawings

E-13GK31

Schematic Diagram Fire Signal Isolation

71111.19

Procedures

AP 16E-002

Post Maintenance Testing Development

21A

71111.19

Procedures

INC C-0063

ESFAS Cabinets SA036C, SA036D, and SA036E Power

Down/Power Up

5B

71111.19

Procedures

MEG EOOP-15

Auxiliary Time Delay Relay (TDR) Testing

71111.19

Procedures

STN FP-402B

Train B Halon System Checkout for KC-230

71111.19

Procedures

STS EN-100A

Containment Spray A Inservice Pump Test

71111.19

Procedures

STS GK-004A

Class 1E A/C Unit Train A Operability Test

71111.19

Procedures

STS MT-074

SGK05A Heat Exchanger Inspection

7A

71111.19

Procedures

SYS GK-004A

Class 1E A/C Unit Train A Operability Test

71111.19

Work Orders

WO

17-422035-000, 17-422035-001, 20-465834-000,

21-469562-000, 21-471648-003, 21-471648-005,

21-471648-006, 21-471861-000, 21-472946-000,

21-472974-000, 21-474284-001, 22-476871-000,

2-476871-001, 22-476871-002, 22-476871-003,

2-477088-000

71111.22

Corrective Action

Documents

Condition Reports

2003-1999, 127972, 131143, 132915, 136319, 136755,

137903, 141686, 10010642, 10012028, 10012905,

10013003, 10013030, 10013207, 1013219, 10013220

71111.22

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

10011968, 10012698

71111.22

Drawings

M-12BB01

Piping and Instrumentation Diagram Reactor Coolant

System

71111.22

Drawings

M-12EF02

Piping and Instrumentation Diagram Essential Service Water

System

71111.22

Drawings

M-12EM01

Piping and Instrumentation Diagram High Pressure Coolant

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Injection System

71111.22

Drawings

M-12EM02

Piping and Instrumentation Diagram High Pressure Coolant

Injection System

71111.22

Drawings

M-12KA01

Piping and Instrumentation Diagram Compressed Air

System

71111.22

Miscellaneous

E-11028

Relay Setting Tabulation systems NK and NN

71111.22

Miscellaneous

WCOP-02

Inservice Testing Program for Pumps, Valves, and Snubbers

71111.22

Miscellaneous

WCRE-34

Fourth 10 year Interval Inservice Testing Basis Document

71111.22

Procedures

AI 29B-003

Guidance to Prevent Unacceptable Preconditioning Prior to

Testing

71111.22

Procedures

AP 29G-001

RCS Unidentified Leak Rate Monitoring Program

71111.22

Procedures

M-12BG01

Piping and Instrumentation Diagram Chemical and Volume

Control System

71111.22

Procedures

M-12BG03

Piping and Instrumentation Diagram Chemical and Volume

Control System

71111.22

Procedures

M-12EP01

Piping and Instrumentation Diagram Accumulator Safety

Injection

71111.22

Procedures

OFN RJ-023

NPIS Malfunctions

71111.22

Procedures

STN RJ-001

Verification of Operability of Computer Processes

71111.22

Procedures

STS BB-004

RCS Water Inventory Balance

71111.22

Procedures

STS BB-006

RCS Water Inventory Balance Using NPIS Computer

71111.22

Procedures

STS CR-001

Shift Log for Modes 1, 2, and 3

113

71111.22

Procedures

STS EF-210A

ESW System Inservice Check Valve Test

2A

71111.22

Procedures

STS MT-018

Weekly Inspection of 125 VDC Lead-Calcium Batteries

XX

71111.22

Procedures

STS MT-020

25 Volt DC Battery Charger Operational Test

26B

71111.22

Procedures

STS NB-005

Breaker Alignment Verification

71111.22

Procedures

STS PE-019E

RCS Isolation Check Valve Leak Test

71111.22

Procedures

STS PE-019G

BB9448A/B/C/D, SI/Accum RCS Lope Check Valves Leak

Test

71111.22

Procedures

STS SE-001

Power Range Adjustment to Calorimetric

36A

71111.22

Procedures

STS SE-002

Manual Calculation of Reactor Thermal Power

71111.22

Procedures

STS SF-002

Core Axial Flux Difference

71111.22

Procedures

SYS EM-002

SI System Depressurization

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.22

Procedures

SYS EM-121

ECCS Check Valve Leak Check

71111.22

Procedures

WCRE-38

Surveillance Frequency Control Program Surveillance Test

Interval List

71111.22

Work Orders

WO

18-441067-000, 18-444596-000, 19-450375-000,

19-452686-000, 19-454637-000, 20-460401-000,

20-461183-000, 20-461995-000, 20-463677-000,

20-467103-000, 20-467632-000, 21-468267-000,

21-469215-000, 21-469562-000, 21-469562-001,

21-469562-002, 21-469562-003, 21-469562-004,

21-473112-000, 21-474193-000, 21-474388-000,

2-478402-000

71152A

Corrective Action

Documents

Condition Reports

93-1687, 140866, 141515, 141532, 142239, 10009587,

10011538, 10011562

71152A

Drawings

E-13BG01

Schematic Diagram Centrifugal Charging Pump A

71152A

Drawings

E-13EM02

Schematic Diagram Boron Injection Tank Inlet Iso. Valve

EMHV8803A

71152A

Drawings

E-13GL05

Schematic Diagram Pump Room Cooler

71152A

Drawings

E-13NG11

Schematic Diagram 480V L.C. Main Feeder Breaker Class

1E Low Voltage System

71152A

Drawings

M-12EM02

Piping and Instrumentation Diagram High Pressure Coolant

Injection System

25