IR 05000390/2021004

Integrated Inspection Report 05000390/2021004 and 05000391/2021004

ML22045A038
Person / Time
Site:	Watts Bar   (NPF-090, NPF-096)
Issue date:	02/10/2022
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
References
IR 2021004
Download: ML22045A038 (22)

Text

February 10, 2022

SUBJECT:

WATTS BAR NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000390/2021004 AND 05000391/2021004

Dear Mr. Barstow:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant. On February 1, 2022, the NRC inspectors discussed the results of this inspection with Mr. Anthony Williams and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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

Sincerely,

/RA/

Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects

Docket Nos. 05000390 and 05000391 License Nos. NPF-90 and NPF-96

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000390 and 05000391

License Numbers:

NPF-90 and NPF-96

Report Numbers:

05000390/2021004 and 05000391/2021004

Licensee:

Tennessee Valley Authority

Facility:

Watts Bar Nuclear Plant

Location:

Spring City, TN 37381

Inspection Dates:

October 01, 2021 to December 31, 2021

Inspectors:

W. Deschaine, Senior Resident Inspector

J. Diaz-Velez, Senior Health Physicist

C. Fontana, Emergency Preparedness Inspector

D. Lanyi, Senior Operations Engineer

M. Magyar, Reactor Inspector

K. Miller, Resident Inspector

A. Nielsen, Senior Health Physicist

W. Pursley, Health Physicist

S. Sanchez, Senior Emergency Preparedness Insp

D. Simpkins, Sr. Tech Training Program Specialist

J. Walker, Emergency Response Inspector

Approved By:

Thomas A. Stephen, Chief

Reactor Projects Branch 5

Division of Reactor Projects

SUMMARY

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

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near rated thermal power (RTP) from the beginning of the inspection period until October 29th, when it was shutdown for a planned refueling outage (U1R17). The unit remained in the outage until it was restarted on December 3rd. Unit 1 continued power ascension until December 9th, when the unit reached RTP, and remained there for the remainder of the inspection period.

Unit 2 began the inspection period shutdown for a mid-cycle outage (F214) until it was restarted on October 1st. Unit 2 continued power ascension until October 10th, when the unit reached 95 percent RTP, and remained there for the remainder of the inspection period due to steam generator degradation.

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 on-site 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

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:

Unit 1 & 2 Refueling Water Storage Tanks and Unit 1 & 2 Main steam and Feedwater Lines that are exposed to the outside on December 23, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 1 Residual Heat Removal (RHR) System during the first week of the refueling outage on November 3, 2021.

(2) Spent Fuel Pool Cooling System during core empty period for U1R17, November 10-12, 2021.

(3) Unit 2 A train Emergency Diesel Generator (EDG) on December 1, 2021.

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 Auxiliary Feedwater system on October 7, 2021.

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) EDG Building Board Rooms, Exhaust Rooms, and Intake Rooms 2nd floor on October 5, 2021.

(2) Auxiliary Building Elev. 757', Shutdown Board Rooms on October 6, 2021.

(3) Auxiliary Building Corridor Elev. 713' on October 6, 2021.

(4) Unit 2 Control Rod Drive Equipment Room, Pressurizer Heater Transformer Room, and Emergency Gas Treatment Filter Room on October 7, 2021.

(5) Unit 1 Lower Containment on October 30, 2021.

(6) Unit 1 Annulus on November 10, 2021.

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) Unit 1 and 2 auxiliary building elev. 757', shutdown board rooms

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Component Cooling System (CCS) Heat Exchanger C

===71111.08P - Inservice Inspection Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01)===

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from November 1 - November 18, 2021:

1. Ultrasonic Testing (UT)

a. RCS-016, Pipe to Elbow, Class 1 (reviewed)b. MRP-146-CL-2, Pipe to Nozzle, Augmented (reviewed)c. MRP-146-DR-4, Socket Elbow to Pipe, Augmented (reviewed)

2. Penetrant Testing (PT)

a. SWHXH-1-IA, Welded Attachment, Class 2 (reviewed)

3. Visual Examination (VT)

a. Reactor Vessel Closure Head (RVCH), N-729-6 (reviewed)

The Inspectors evaluated the licensees boric acid corrosion control program performance.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) Annual Review of Licensee Requalification Examination Results: The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 13, 2021, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.

The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on August 27, 2021.

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 the Unit 1 refueling outage shutdown on October 29, 2021 and the Unit 1 B train Blackout testing on November 1, 2021.

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

(1) The inspectors observed and evaluated a licensed operator requalification simulator scenario on October 14, 2021. Additionally, the inspectors observed and evaluated a licensed operator requalification simulator scenario on October 21, 2021. Both of these observations make up one sample.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 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) System 030-G Aux Bldg Gas Treatment System

(2) System 074-B - RHR Emergency Core Cooling System (ECCS) (Unit 2)

(3) System 003B-B Auxiliary Feedwater System (Unit 2 TDAFW)

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 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) Unit 1 Blackout testing & Mode 5 & 6 activities during the week of October 31, 2021.

(2) Technical Specification (SR 3.0.3) required risk evaluation due to Unit 1 B train safety injection signal to F-B and H-B Essential Raw Cooling Water (ERCW) pumps not being tested during 0-SI-82-4 on November 11, 2021.

(3) Risk assessment for (week of) December 6, 2021, with B Main Control Room Chiller Outage (planned) and the 1B EDG declared inoperable (emergent).

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) Leakage of Kerotest globe valve stem inside Unit 2 containment; Condition Reports (CRs) 1725073, 1724851

(2) Unit 2 ERCW pipe leak on the 2A-A ERCW strainer; CRs 1721374, 1722767

(3) Trip of 2A-A EDG while unloading during performance of a monthly test 0-SI-82-12-A; CR 1738430

(4) The fouling factor of CCS Heat Exchanger C tested on 10/30/21 was greater than acceptance criteria; CR 1732724

(5) Unit 1 Control Room Level Indicator, 1-LI-3-156 (Steam Generator #2 Auxiliary Feedwater Level Indicator), failed full-scale; CRs 1743606 and 1743845

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) WBN-18-126 - Unit 2 permanent modification involving rerouting/protecting cables for the solenoid valve that actuates Steam Generator (SG) Power Operated Relief Valve for SG 3 Main Steam Header Pressure.

(2) Design Equivalent Change Package DEC 66688 - EDG Jacket Water Heat Exchanger Replacement.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

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

(1) Work Orders (WOs) 121880323 & 122346076, Unit 2 Pressurizer PORV (2-FCV-68-334-B) replacement on October 10 and 19, 2021.

(2) WO 121491678, 1-SI-63-905, Boron Injection Check Valve Flow Test During Refueling Outages, following replacement of the 1B-B Charging Pump (CCP) Motor, on November 14, 2021

(3) WO 121492608, Engineering Change Package WBN-19-760 Stage 2 Post Modification Testing for WBN-1-LCV-3-171

(4) WO 121491970, 1-SI-3-902, Turbine Driven Auxiliary Feedwater Pump 1A-S Quarterly Performance Test, was completed on December 3, 2021 following the disassembly and inspection of the TDAFW Trip & Throttle Valve, 1-FCV-001-0051-S.

(5) WO 121492548, 1-SI-74-905-B, Residual Heat Removal Pump 1B-B Comprehensive Test during refueling outages, following replacement of the 1B-B RHR Pump Motor, on November 15, 2021.

(6) WO 121493637, 1-SI-3-923-B, Auxiliary Feedwater Pump 1B-B Comprehensive Pump Test, following replacement of the 1B-B Auxiliary Feedwater Pump Motor, on November 28, 2021.

(7) WO 122503680, Unit 1 CVCS Normal Charging Check Valve, 1-CKV-62-659-S, NRC identified Boric Acid Leak, involved replacement of the valve bonnet to body gasket on November 7, 2021. A VT-2 examination was performed with the RCS at NOP/NOT on December 3, 2021 as the PMT, with no leakage observed.

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated refueling outage U1R17 activities from October 29 to December 4, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) WO 121491710, 1-SI-63-907, Residual Heat Removal Hot Leg and Cold Leg Injection Check Valve Testing during Refueling outages.

(2) WO 121493053, 0-SI-82-4, Loss of Off-site Power with Safety Injection - 1B-B EDG.

(3) WO 121491679, 1-SI-63-906, Safety Injection Check Valve Full-Flow Testing During Refueling outages.

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) WO 121493711, 1-SI-43-701-B, Containment Isolation Valve Leak Rate Test Sampling System (X-85B).

Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1) WO 121491641, 1-SI-61-5, 18 Month Ice Condenser Lower Inlet Doors Inspections.

71114.01 - Exercise Evaluation

Inspection Review (IP Section 02.01-02.11) (1 Sample)

(1) The inspectors evaluated the biennial emergency plan exercise during the week of October 18, 2021. The exercise scenario simulated a steam generator (SG) tube leak on SG#1, which after 15 minutes, met the criteria for declaration of an Unusual Event. As the leak continued to increase, a manual reactor trip and safety injection occurred, which met the conditions for declaration of an Alert on Unit 1. A short time later, a simulated trip of a reactor coolant pump caused reactor fuel damage due to introduction of foreign material (i.e., loose parts), which met the conditions for declaration of a Site Area Emergency. Finally, a power operated relief valve on SG#1 piping failed open, which met the conditions for declaration of a General Emergency, and allowed the Offsite Response Organizations to demonstrate their ability to implement emergency actions. This exercise scenario also included a beyond design basis demonstration related to loss of spent fuel pool water inventory.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of October 18, 2021. This evaluation does not constitute NRC approval.

71114.08 - Exercise Evaluation Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed and evaluated in-office, the proposed scenario for the biennial emergency plan exercise at least 30 days prior to the day of the exercise.

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area,

(2) Controls for non-fuel items stored in spent fuel pool.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Unit 1 reactor head modification work.

(2) Unit 1 seal table eddy current.

(3) Unit 1 reactor head detensioning.

(4) Unit 1 refueling activities.

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Unit 1 under-vessel access.

(2) Tritiated drain collector tank.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensees radiological work planning for Unit 1 Refueling Outage 17 (U1R17).

(1) U1R17 - As Low As Reasonably Achievable (ALARA) Plan #2021-125, Simplified Head Assembly Modification

(2) U1R17 - ALARA Plan #2021-123, Rx Disassembly/Assembly

(3) U1R17 - ALARA Plan #2021-116, Scaffolding

(4) U1R17 - ALARA Plan #2021-128, Radiation Protection

(5) U1R17 - ALARA Plan #2021-142, Maintenance Services

Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (3 Samples)

The inspectors evaluated dose estimates and exposure tracking.

(1) Radiological outcome evaluation for ALARA Plan #2020-218 (Unit 2 Refueling Outage 3 (U2R3) Valve Maintenance)

(2) Radiological outcome evaluation for ALARA Plan #2020-219 (U2R3 Steam Generator Maintenance)

(3) Radiological outcome evaluation for ALARA Plan #2020-223 (U2R3 Rx Disassembly/Assembly)

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls for the following activities:

(1) Total Effective Dose Equivalent ALARA evaluation for ALARA Plan #2021-144, U1R17 Refuel Floor Miscellaneous - Auxiliary Building Transfer Canal Entries

(2) U1R17 reactor vessel re-assembly - upper internals movement

Radiation Worker Performance (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance during work activities.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Tool decontamination fume hoods.

(2) Main control room emergency ventilation system.

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) High Efficiency Particulate Air (HEPA) units used to support seal table eddy current testing.

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Internal dosimetry evaluation related to condition report 1733322.

(2) Ten in-vitro tritium bioassay results for the period from January 2020 through October 2021.

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Five declared pregnant worker dosimetry records from May 2019 to October 2021.

(2) One multi-Badge dosimetry record from May 2019 to October 2021.

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (9 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Area radiation monitors in the auxiliary building and the Unit 1 and Unit 2 control room.

(2) Geiger Mueller survey instruments ready for use in the radiation protection (RP)instrument lab

(3) Portable ion chambers stored ready for use in the RP calibration lab and the RP control point on the refuel floor.

(4) Continuous air monitors positioned at various locations in the auxiliary building and the control room

(5) Portal monitors at the exit to the protected area.

(6) Personnel contamination monitors at the auxiliary building radiological control area exit.

(7) Benchtop Alpha/Beta Sample Counter in use on the refuel floor and RP instrument lab.

(8) Portable survey instrument with alpha probe at the RP survey point on the refueling floor.

(9) Observed source checks on a neutron survey meter, extendable gamma survey meter, ion chamber, benchtop alpha/beta smear counter, and portable alpha survey instrument.

Calibration and Testing Program (IP Section 03.02) (15 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Unit 1 Upper Containment High Range Post Accident Radiation Monitor, 1-90-271 Train A, Work Order (W/O) 121162225 and W/O 11988754.

(2) Unit 1 Lower Containment High Range Post Accident Radiation Monitor 1-LPR-90-273 Train A, W/O 1202413740 and W/O 119065041.

(3) Unit 1 and 2 Control Room Area Monitor, 0-LPR-90-135, W/O 119759726.and W/O

===120981624.

(4) TVA #842482, tritium continuous air monitor, 07/20/2021

(5) TVA #848558, alpha/beta smear counter, 08/02/2021

(6) TVA #848617, air sampler, 09/07/2021

(7) TVA # 842470, continuous air monitor, 07/15/2021.

(8) TVA # 860815, frisker, 01/27/2021

(9) TVA #951279, alpha survey instrument, 07/12/2021

(10) TVA #951234, Geiger/Mueller survey instrument, 07/12/2021

(11) TVA #848513, portal monitor, 03/08/2021

(12) TVA #848220, personnel contamination monitor, 04/19/2021

(13) Auxiliary Building Gas Treatment System Filter Test Train A (W/O 120850600) and Train B (W/O 121360402)

(14) TVA #848505, small article monitor, 06/24/2021

(15) Whole body counter in Dosimetry office, 06/09/2020

Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03)===

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Unit 1 Shield Building Vent Radiation Monitor, 1-LPR-090-0400, 06/25/2019, (W/O

===119541434) and on 02/13/2021 (W/O 119065041)

(2) Waste Disposal System Liquid Disposal System Effluent Monitor, O-LPR-90-122 on 01/09/2020, (W/O 120498154) and on 07/20/2021, (W/O 121716468)

(3) Calibration of the Unit 2 Shield Building Vent Flow Monitor Loop 2-LPF-90-400, W/O 120065944 and W/O

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) Unit 1 January 2020 - September 2020

(2) Unit 2 January 2020 - September 2020

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 January 2020 - September 2020

(2) Unit 2 January 2020 - September 2020

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 January 2020 - September 2020

(2) Unit 2 January 2020 - September 2020

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) August 15, 2020 through October 12, 2021

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) August 15, 2020 through October 12, 2021

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) Unit 1 (October 1, 2020, through June 30, 2021)

Unit 2 (October 1, 2020, through June 30, 2021)

EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)

(1) Unit 1 (October 1, 2020, through June 30, 2021)

Unit 2 (October 1, 2020, through June 30, 2021)

EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) Unit 1 (October 1, 2020, through June 30, 2021)

Unit 2 (October 1, 2020, through June 30, 2021)

71152 - Problem Identification and Resolution (PI&R)

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in human performance errors that might be indicative of a more significant safety issue. None were identified during the past six months.

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

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

(1) Steam Generator level control valve issues; CRs 1683845, 1687846, and 1709741.

(2) Intake Pumping Station strainer room water intrusion issue; CR

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On February 1, 2022, the inspectors presented the integrated inspection results to Mr.

Anthony Williams and other members of the licensee staff.

• On October 22, 2021, the inspectors presented the Emergency Preparedness Exercise Inspection inspection results to Mr. Tony Williams and other members of the licensee staff.

• On November 18, 2021, the inspectors presented the Radiation protection inspection exit meeting inspection results to T. Williams and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Drawings

0-45W727

Wiring Diagram 6900V Diesel Generators Single Line

Revision 9

0-47W855-1

Mechanical Flow Diagram Fuel Pool Cooling and Cleaning

System

Revision 19

1-47W810-1

Flow Diagram Residual Heat Removal System - Unit 1

Revision 21

WBN Drawings

2-47W803-1 Rev. 36, 2-47W803-101, 2-47W803-1-ISI, 2-

47W803-ISI

Miscellaneous

10.4.9

SBN FSAR Section

3-OT-STG0821

Operations Student Training Guide for the Diesel Generator

Revision 10

SDD-N3-3B-4002

Auxiliary Feedwater System Description

SDD-N3-82-4002

System Description for the Standby Diesel Generator System Revision 26

WBN-N3-74-4001 Residual Heat Removal System Description

Revision 20

WBN-N3-78-4001 Spent Fuel Pool Cooling and Cleaning System System

Description

Revision 25

WBN-N3-79-4001 Fuel Handling and Storage System System Description

Revision 24

Procedures

0-AOI-45

Loss of Spent Fuel Pool Level or Cooling

Revision 9

0-SOI-78.01

Spent Fuel Pool Cooling and Cleaning System

Revision 36

0-SOI-78.01-1P

Spent Fuel Pool Cooling and Cleaning System - Power

Checklist

Revision 10

0-SOI-78.01-1V

Spent Fuel Pool Cooling and Cleaning System - Valve

Checklist

Revision 10

0-SOI-82.03

System Operating Procedure for the 2A-A Diesel Generator

(DG)

Revision 21

0-SOI-82.03 ATT

1P

Diesel Generator (DG) 2A-A Power Checklist 82.03-1P

Revision 0

0-SOI-82.03 ATT

1V

Diesel Generator (DG) 2A-A Valve Checklist 82.03-1V

Revision 15

1-AOI-14

Loss of RHR Shutdown Cooling

Revision 7

1-SOI-74.01

Residual Heat Removal System

Revision 19

1-SOI-74.01-

1,2,3P

Residual Heat Removal System - Power Checklist

Revision 0

1-SOI-74.01-

1,2,3V

Residual Heat Removal System - Valve Checklist

Revision 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

WBN-2-SOI-3.02

Auxiliary Feedwater System Operating Instruction

71111.05

Corrective Action

Documents

1678126

Condition Report

Fire Plans

WBN Prefire

Plans

DGB-0-742-01 Rev. 4, DGB-0-760-01 Rev. 3/4, AUX-0-757-

Rev. 2, AUX-0-757-02 Rev. 6/4, AUX-0-757-03 Rev. 9/4,

AUX-0-757-04 Rev. 4

Miscellaneous

Fire Protection Reports

WBN FHAR Part

Introduction, Table I-1 Summary Compliance Fire Protection

WBN-02-2021-

031-002

Temporary Modifiction

Work Orders

21997042

Work Order

71111.06

Miscellaneous

MDN-000-999-

2008-0146

WBN Probabilistic Risk Assessment - Internal Flooding

Analysis Notebook

Revision 3

WB-DC-40-31.51

Evaluating the Effects of Flooding due to Moderate Energy

Pipe Failures Inside and Outside Containment

MDN-000-999-2008-0146, Rev. 03 - WBN Probabilistic Risk

Assessment - Internal Flooding Analysis Notebook

Revision 5

71111.07A Work Orders

21492368

0-TI-79.703, Component Cooling System Heat Exchanger C

Performance Test

11/07/2021

71111.12

Corrective Action

Documents

Condition Reports 1652081, 1654732, 1684512

Miscellaneous

Associated MRC Log Entries

CDEs

23, 1734, 1743

Procedures

0-TI-119

Maintenance Rule Performance Indicator Monitoring,

Trending, and Reporting - 10CFR50.65

Revision 11

NPG-SPP-03.4

Maintenance Rule Performance Indicator Monitoring,

Trending and Reporting - 10CFR50.65

Revision 4

Work Orders

Work Orders

21761298, 121761309

71111.13

Corrective Action

Documents

1736039

Condition Report

Miscellaneous

TS3.9.5

One RHR loop shall be OPERABLE and in operation.

Procedures

1-PI-OPS-1-PE

Protected Equipment

NPG-SPP-07.3

Work Activity Risk Management Process

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.15

Corrective Action

Documents

Condition Reports 1721374, 1722767, 1724851, 17250731743606, 1743845

Miscellaneous

10CFR Part 21

Report - 2006-23

Incorrect Identification of the Material Used to Manufacture

Y-Globe Valve

1988-012

NRC Information Notice

7839

IRS Report

Operability

Evaluations

Past Operability Evaluation Documentation for CR 1721374

10/06/2021

Prompt Determination of Operability Documentation for CR

1743845

Procedures

0-TRI-67-903-A

System Leakage Test, ERCW At Intake Pumping Station,

Train A

Work Orders

Work Orders

2409059, 122443321, 122607694

71111.18

Corrective Action

Documents

Condition Report

1453939

Engineering

Changes

DEC 66688

Design Equivalent Change Package EDG Jacket Water Heat

Exchanger Replacement

Revision 4

WBN-18-126

SG PORV App R concerns

Revision 1

71111.19

Corrective Action

Documents

Condition Reports 1655007, 1632674, 1666144, 1663015, 1729956, 1732175,

1732178, 1736039

Miscellaneous

STS WO 122393586, 2-SI-68-904-B

Procedures

Procedures

2-MI-68.021 Rev. 6, 0-MI-57.107 Rev. 3, 0-MI-57-102 Rev.

6, 0-MI-57.042 Rev. 1

Work Orders

Work Orders

21492548, 121577666, 121366844, 121577582,

2035785, 121491970, 122503680

71111.22

Corrective Action

Documents

Condition Report

29956, 1732412, 1732431, 1732694, 1732951, 1733448,

1734460, 1734889

Miscellaneous

47W625-1

Flow Diagram - Radiation Sampling Sys Aux & Reactor

Building

Procedures

1-SI-43-701-B

Containment Isolation Valve Leak Rate Test Sampling

System (X-85B)

Revision 16

1-SI-61-5

Month Ice Condenser Lower Inlet Doors Inspections

Revision 16

1-SI-63-906

Safety Injection Check Valve Full-Flow Testing During

Refueling outages

Revision 34

1-SI-63-907

Residual Heat Removal Hot Leg and Cold Leg Injection

Revision 34

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Check Valve Testing during Refueling outages

Work Orders

Work Orders

21493053 Rev. 76, 121492209 Rev. 8

71124.01

Corrective Action

Documents

CR 1721499

CR 1734382

CR 1735549

Corrective Action

Documents

Resulting from

Inspection

CR 1733297

Procedures

NISP-RP-005

Access Control for High Radiation Areas

Revision 1

Radiation

Surveys

WBN-M-

211103-24

U1 Lower Containment Seal Table

11/3/21

Radiation Work

Permits (RWPs)

21150012

U1R17 - U1 Lower Containment High Radiation Areas

71124.02

ALARA Plans

ALARA Plan

1. 2020-218

Activities associated with mechanical (including PORVs &

Safeties), AOV, MOVAT valve maintenance during the

U2R3.

2/08/2020

Corrective Action

Documents

CR 1647220

CR 1647220

10/31/2020

CR 1650643

CR 1650643

11/16/2020

CR 1652218

CR 1652218

11/23/2020

CR 1652437

CR 1652437

01/26/2021

CR 1682399

CR 1682399

04/08/2021

CR 1721012

CR 1721012

09/17/2021

Procedures

NPG-SPP-05.1

Radiological Controls

Rev. 15

NPG-SPP-05.2

ALARA Program

Rev. 11

NPG-SPP-05.2.1

Operational ALARA Planning and Controls

Rev. 8

NPG-SPP-05.2.6

Radiological Risk Management

Rev. 5

Radiation Work

Permits (RWPs)

21140001

U1R17 OUTAGE - U1 AUX BLDG AND U1 ANNIJLUS

RADIATION AREAS (INCLUDING ALL RCAs) - All Work

Groups performing Outage Specific Activities.

Rev. 0

21140002

U1T17 OUTAGE - U1 AUX BLDG & U1 ANNULUS HIGH

RADIATION AREAS - All work groups performing outage

specific activities.

Rev. 0

21140003

U1T17 OUTAGE - U1 AUX BLDG & U1 ANNULUS LOCKED

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

HIGH RADIATION AREAS - All work groups performing

outage specific activities.

21140011

U1R17 U1 AUX BUILDING, U1 ANNULUS, AND ALL

OTHER RCAs. - ALL WORK GROUPS PERFORMING

OUTAGE

ACTWITIES

Rev. 0

71124.03

Engineering

Evaluations

Air Compressor

Serial Number

184372

Air Quality Analysis Report

06/25/21

Procedures

RCI-107

Respiratory Protection Equipment Inspection, Maintenance,

Issuance and Accountability

Revision 31

71124.04

Corrective Action

Documents

CR 1524681

CR 1524681

06/13/2019

CR 1555061

CR 1555061

10/07/2019

CR 1555065

CR 1555065

10/07/2019

CR 1555375

CR 1555375

10/08/2019

CR 1621288

CR 1621288

07/07/2020

Procedures

RCDP-10

Personnel Contamination Event Documentation

Rev. 9

RCDP-13

Centralized Inprocessing Facility Activities

Rev. 7

RCDP-15

Dosimetry Operations

Rev. 5

RCDP-7

Bioassay and Internal Dose Program

Rev. 10

RCI-111

Special Exposure Monitoring

Rev. 17

RCI-130

Personnel Monitor Alarm Response and Nuclear

Pharmaceutical Treatments

Rev. 21

RCTP-105

Personnel In-processing and Dosimetry Administrative

Processes

Rev. 11

71124.05

Corrective Action

Documents

Resulting from

Inspection

29939

Procedures

1-CM-13.12

Obtaining A Post-Accident Shield Building Vent Iodine And

Particulate Or Tritium Sample

Revision

0002

CM 9.83

ORTEC Gamma Detector Quality Control

Revision

0005

RCDP-8

Radiological Instrumentation/Equipment Controls

Revision

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

0009

71151

Calculations

Gas Status

Summary Report

01/01/21 -

10/12/21

Corrective Action

Documents

CR 1664315

CR 1708516

CR 1708516

07/17/2021

CR 1711837

CR 1711837

08/03/2021

CR 1724930

CR 1724930

09/30/2021

71152

Corrective Action

Documents

Condition Reports 1721774, 1744223, 1744722, 1743980, 1743984, 1742821