IR 05000456/2021002

Integrated Inspection Report 05000456/2021002 and 05000457/2021002

ML21204A069
Person / Time
Site:	Braidwood
Issue date:	07/22/2021
From:	Hironori Peterson Region 3 Branch 3
To:	Rhoades D Exelon Generation Co, Exelon Nuclear
References
IR 2021002
Download: ML21204A069 (27)

Text

July 22, 2021

SUBJECT:

BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2021002 AND 05000457/2021002

Dear Mr. Rhoades:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On July 13, 2021, the NRC inspectors discussed the results of this inspection with Mr. John Keenan, Site Vice President, 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/

Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000456 and 05000457 License Numbers: NPF-72 and NPF-77 Report Numbers: 05000456/2021002 and 05000457/2021002 Enterprise Identifier: I-2021-002-0063 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station Location: Braceville, IL Inspection Dates: April 01, 2021 to June 30, 2021 Inspectors: D. Betancourt-Roldan, Senior Resident Inspector (Byron)

R. Bowen, Illinois Emergency Management Agency J. Bozga, Senior Reactor Inspector G. Edwards, Health Physicist M. Holmberg, Senior Reactor Inspector D. Kimble, Senior Resident Inspector (Braidwood)

P. Smagacz, Resident Inspector Approved By: Hironori Peterson, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY

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

List of Findings and Violations

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

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period operating at approximately 89 percent power with end-of-cycle power coast down operations in progress. On April 5, 2021, the unit was shut down for its planned 22nd refueling outage (A1R22). Following completion of refueling and other maintenance activities, the reactor was restarted and taken critical on April 23, 2021, and the main electrical generator was synchronized to the power grid on April 24, 2021. The unit reached full power operation on April 27, 2021. On May 22, 2021, power was reduced to approximately 85 percent to facilitate maintenance on the condensate system. Unit 1 returned to full power later that same day. Just after midnight on June 21, 2021, Unit 1 experienced an automatic trip from full power due to a lightning strike in the stations main switchyard during a severe thunderstorm. After post-trip checks verified that the condition of the unit was acceptable for restart, the reactor was taken critical in the evening on June 21, 2021, and the main electrical generator was synchronized to the power grid on the morning of June 22, 2021. The unit reached full power operation just before midnight on June 22, 2021, and remained operating at or near full power for the remainder of the inspection period.

Unit 2 began the inspection period operating at full power. On May 7, 2021, the unit reduced power to approximately 68 percent to facilitate replacement of a failed relief valve on the 23C Low Pressure (LP) Feedwater (FW) Heater. The unit returned to full power operation the following day, and with the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, it remained operating at or near full power for the remainder of the inspection period.

INSPECTION SCOPES

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

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems during the weeks ending June 26 through June 30, 2021.

71111.04 - Equipment Alignment

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

The inspectors evaluated system configurations during partial physical alignment verifications of the following systems/trains:

(1) The spent fuel pool (SFP) cooling system while the Unit 1 reactor core was offloaded to the SFP for the A1R22 refueling outage, during the week ending April 17, 2021.

(2) The Unit 1 component cooling system (CC) during maintenance on 1CC9743A, during the week ending May 8, 2021.

(3) The 2A Emergency Diesel Generator (EDG) while the unit's station auxiliary transformer was undergoing planned maintenance, during the week ending May 15, 2021.

(4) The 2A Safety Injection (SI) Train while the 2B SI Train was out-of-service for maintenance, during the week ending June 19, 2021.

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

The inspectors evaluated system configurations during a complete physical alignment verification of the following system/train:

(1) The Unit 1 residual heat removal (RH) system, during the weeks ending April 10 through April 24, 2021. This activity completed the partial inspection sample that was documented in NRC Inspection Report 05000456/2021001; 05000457/2021001 (ADAMS Accession No. ML21106A208).

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting physical inspections and reviews to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) The Unit 1 Containment, 377' Elevation, Inside Missile Barrier area, during the week ending April 17, 2021.

(2) The Unit 1 Containment, 401' Elevation, Outside Missile Barrier area, during the week ending April 17, 2021.

(3) The Unit 1 Containment, 426' Elevation, during the week ending April 17, 2021.

(4) The Unit 1 Auxiliary Building, 330' Elevation, 1A/2A Essential Service Water (SX)

Pump Room while performing maintenance/hot work on 1A SX Pump, during the week ending April 17, 2021.

(5) The Unit 1 Containment, 401' Elevation, Inside Missile Barrier area while performing maintenance/hot work on reactor coolant pumps, during the week ending April 17, 2021.

(6) The Unit 1 Auxiliary Building, 383' Elevation, 1B Auxiliary Feedwater (AF) Pump Room, during the week ending May 8, 2021.

(7) The Unit 2 Switchgear area, 451' Elevation, Miscellaneous Electrical Equipment Room, during the week ending May 15, 2021.

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified the reactor coolant system boundary and risk significant piping system boundaries were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 7, 2021 to April 16, 2021:

03.01.a - Nondestructive Examination and Welding Activities.

• Ultrasonic (UT) examination of reactor coolant pipe welds 1RC-35-02, 1RC-16-02, 1RC-35-04

• UT examination of pressurizer nozzle to shell welds 1PZR-01-N2, 1PZR-01-N3

• UT examination of reactor vessel hot leg outlet nozzle to safe-end welds 1RV-01-022,1RV-01-025 and 1RV01-029

• UT examination of steam generator A girth weld 1SG-05-SGC-02

• UT examination of main steam piping welds 1MS-04-34, 35, 36, 37 and 38

• UT of feedwater pipe to elbow welds 1FW-04-34, 35, 37 and 38

• Visual examination for leakage (VT-2) of 1RC-20-B1 and 1RC-27-B1 bolted connections

• Welds 1 and 4, 1SX252 valve replacement, (Work Order (WO) 04817111-01)

• Welds 11-1 and 6-1,1RC8042B valve replacement, (WO 05046086-01)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

• Bare Metal Visual (VE) examination of the reactor vessel upper head penetrations nozzles 2, 5, 13 and 59 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

• Boric Acid Leakage Evaluation on Component 1SI023A (adapter and instrument cap)

• Boric Acid Leakage Evaluation on Component 1PS9356A (reactor coolant loop sample isolation valve assembly)

• Boric Acid Leakage Evaluation on Component 1RC8042B (reactor coolant loop 1B equalization line main isolation valve)

• Corrective Actions to Leakage at Valve 1RC8042B (Issue Report (IR)

===04346974, AR 04391367)

• Corrective Actions to Leakage Downstream of 1SI023A (IR 04345873)

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

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

=

The inspectors observed and evaluated the following licensed operator activities in the control room:

(1) Various activities involving on-watch operations crews. These activities included, but were not limited to:

• Shutdown of Unit 1 for the A1R22 refuel outage, during the week ending April 10, 2021.

• Unit 1 reactor coolant system draining in support of A1R22 refuel outage reactor vessel head lift, during the week ending April 10, 2021.

• Unit 1 reactor coolant pump startups for A1R22 refuel outage plant heat up, during the week ending April 24, 2021.

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

The inspectors observed and evaluated the following licensed operator training activity:

(1) A complex casualty graded scenario involving a crew of licensed operators was observed in facility's simulator on May 25, 2021.

71111.12 - Maintenance Effectiveness

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance, as well as certain quality control activities, to ensure the following structure, system, and component (SSC) remains capable of performing its intended function:

(1) Maintenance effectiveness and performance history review of the 1/2RC8042 A-D 1.5-inch reactor coolant system equalization line manual isolation valves, during the weeks ending April 17 through May 29, 2021.

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) Evaluation of the work activities and risk associated with the emergent replacement of the 1RC8042D, 1.5-inch manual isolation valve as set forth in WO 4969069, during the week ending April 17, 2021.

(2) Evaluation of the work activities and risk associated with the planned replacement of the 1A SX Pump as set forth in WO 4934317, during the week ending April 17, 2021.

(3) Evaluation of the work activities and risk associated with emergent troubleshooting and repairs to the Unit 2 Control Bank A Rod Drive Power Supply Cabinet with the unit operating at full power as set forth in WO 5149593, during the week ending May 7, 2021.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples 1 Partial)

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

(1) Evaluation of the operability of snubber 1RC01BD-B on the 1B Steam Generator following identification of a hydraulic oil leak as documented in IR 4417398, during the weeks ending April 24 through May 29, 2021.

(2) (Partial)

Evaluation of the operability of the source range nuclear instruments with their high flux trips bypassed during reactor startup as documented in IR 4418688, during the weeks ending May 1 through June 26, 2021.

(3) Evaluation of the operability of Unit 2 Control Bank 'A' rods following receipt of a rod drive urgent failure alarm during semiannual testing as documented in IR 4421424, during the week ending May 7, 2021.

(4) Evaluation of the operability of the 1A Overpower Delta Temperature protection circuit following receipt of a spurious alarm as documented in IR 4421778, during the weeks ending May 7 through May 29, 2021.

(5) Evaluation of the operability of the 1B Overtemperature Delta Temperature and Delta Temperature protection circuits following receipt of spurious indications as documented in IR 4423535, during the weeks ending May 15 through May 29, 2021.

(6) Evaluation of the operability of the 2A Centrifugal Charging Pump due to recurring low differential pressure issues as documented in IR 4423535, during the weeks ending May 22 through June 5, 2021.

71111.18 - Plant Modifications

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

(1 Sample)

The inspectors reviewed and evaluated the following permanent change to the facility that was enacted on the Unit 1 and Unit 2 SX system. The inspectors reviews included an in-depth examination of the licensees use of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, as it was applied to the SX system:

(1) Engineering Change (EC) 632945: 0SX115C Valve and Piping Carbon Fiber Wrap, during the weeks ending April 1 through June 30, 2021. This activity completed the partial inspection sample that was documented in NRC Inspection Report

===05000456/2021001; 05000457/2021001 (ADAMS Accession No.ML21106A208).

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) ===

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

(1) Comprehensive functional and operational testing of the 1A SX Pump following replacement of the pump rotating element as set forth in WO 4934317, during the week ending April 17, 2021.

(2) Comprehensive functional testing of the Unit 1 SI and residual heat removal systems following outage maintenance as set forth in WOs 4980282 and 4983054, during the week ending April 17, 2021.

(3) Functional and operational testing of the 1B Rod Drive Motor-Generator set following multiple actions to balance the motor-generator set as set forth in WO 1953140, during the week ending April 24, 2021.

(4) AF Train 1B testing following outage system maintenance as set forth in WO 4982132, during the weeks ending April 24 through May 1, 2021.

(5) Functional and operational testing of Unit 2 Control Bank 'A' control rods following emergent troubleshooting and repairs as set forth in WO 5149593, during the week ending May 7, 2021.

(6) Low power startup physics testing following reloading of the Unit 1 reactor core for Operating Cycle No. 23 as set forth in WOs 4987491 and 4977795, during the weeks ending April 24 through May 8, 2021.

(7) System leakage testing at normal operating primary pressure and temperature following return of the reactor coolant system to operation after reactor refueling as set forth in WOs 4985624 and 4985631, during the weeks ending April 24 through May 8, 2021.

(8) Functional and operational testing of the 1A EDG following maintenance as set forth in WO 5160533, during the week ending June 26, 2021.

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors reviewed licensee activities and evaluated licensee performance associated with Unit 1 Refuel Outage A1R22, during the weeks ending April 10 through May 1, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Unit 1 Refuel Outage A1R22 emergency core cooling system full flow testing for charging and safety injection as set forth in WO 4983054, during the weeks ending April 10 through May 15, 2021.

(2) Sequencer testing for the 1A EDG for the A1R22 refuel outage as set forth in WO 4803148, during the weeks ending April 10 through May 15, 2021.

(3) Full load rejection testing for the 1A EDG for the A1R22 refuel outage as set forth in WO 4836102, during the weeks ending April 24 through May 29, 2021.

(4) Loss of essential 4 KV bus response testing for the 1A EDG for the A1R22 refuel outage as set forth in WO 5067469, during the weeks ending April 24 through

===May 29, 2021.

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

(1) Observation and assessment of Unit 1 main steam safety valve setpoint testing as set forth in WO 5067469, during the weeks ending April 3 through May 29, 2021.

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

(1) 1BwOSR 3.6.1.1-9: Primary Containment Type C Local Leak Rate Testing for the Unit 1 chemical and volume control system, during the weeks ending April 10 through April 17,

71124.02 - Occupational ALARA Planning and Controls

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls.

(1) The inspectors evaluated items associated with Radiation Work Permit BW-01-21-00613 and associated ALARA documentation for Reactor Head Disassembly and Reassembly during the spring 2021 outage.

(2) The inspectors evaluated items associated with Radiation Work Permit BW-01-21-00623 and associated ALARA documentation for Reactor Cavity Decon during the spring 2021 outage.

(3) The inspectors evaluated items associated with Radiation Work Permit BW-01-21-00612 and associated ALARA documentation for Core Barrel Inservice Inspection (ISI) and all Associated Work Valve Repairs/Inspections during the spring 2021 outage.

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

The inspectors evaluated radiation worker and radiation protection technician performance during:

(1) Fuel move activities.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

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

(1) Unit 1/2 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) Portable high-efficiency particulate air (HEPA) ventilation system used on Reactor Vessel Head Stanchion.

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 licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the internal dosimetry program implementation.

(1) Intake Investigation Form; Plant ID #7080; 04/22/2020 @1300 hours.

(2) Intake Investigation Form; Plant ID #5132; 04/22/2020 @1200 hours.

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

The inspectors evaluated the following special dosimetric situation:

(1) Dose assessment for a declared pregnant worker in 2019.

(2) Dose assessment for a declared pregnant worker in

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors reviewed and verified selected portions of the licensee's performance indicator submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04) ===

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

MS06: Emergency AC Power Systems (IP Section 03.05) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

MS07: High Pressure Injection Systems (IP Section 03.06) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)

(2) Unit 2 (April 1, 2020 - March 31, 2021)

71152 - Problem Identification and Resolution

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

(1) The inspectors conducted a semiannual review of the licensees corrective action program (CAP) for potential adverse trends that might be indicative of a more significant safety concern during the weeks ending June 5 through June 30, 2021. A specific trend related to the Unit 1 Main Steam Isolation Valve (MSIV) Bypass Valves' operation is documented in the Results Section of this report.

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)

The inspectors assessed licensee performance related to the following events:

(1) Review and tracking of licensee actions during the COVID-19 National Emergency declaration as set forth by the President of the United States, during the weeks ending May 15 through June 12, 2021.

(2) Review and assessment of the licensee and plant response to the Unit 1 automatic reactor trip on June 21, 2021, due to a main electrical generator lockout/load rejection as documented in NRC Event Notification (EN) 55320, during the weeks ending June 26 through June 30, 2021.

(3) Review and assessment of the loss of emergency response facility capability due to degradation of the Technical Support Center (TSC) ventilation system on June 24, 2021, as documented in NRC EN 55325, during the weeks ending June 26 through June 30,

INSPECTION RESULTS

Observation: Trend in Unit 1 Main Steam Isolation Valve Bypass Valve 71152 Operation The inspectors performed a review of plant issues, particularly those entered into the licensees CAP over the past several months. During their review, the inspectors noted a trend on Unit 1 involving the operation of MSIV Bypass Valves (1MS101A-D). Upon further inspection, the trend was noted to extend back a few years in time and seemed to be particularly evident most recently on the 1MS101B and 1MS101C valves. Specific CAP entries reviewed by the inspectors included, but were not limited to:

• IR 4201555; 1MS101B Failed To Stroke.

• IR 3968314; 1MS101C "A" Solenoid Replacement - Extent of Condition.

• IR 4256475; 1MS101B Would Not Open when Demanded from its Control Switch.

• IR 4130120; OSP-A - 1MS101C Will Not Go Full Open.

• IR 4427859; 1MS101C Failed to Open when Demanded from Control Switch.

While the inspectors noted that these issues were exclusively limited to the open direction stroke of the valves, which is not part of the components safety function, the recurring nature of issues in the open direction without a thorough understanding of the trend might suggest the presence of an underlying component reliability issue.

The inspectors did not identify any findings or violations of NRC requirements in the course of their review.

EXIT MEETINGS AND DEBRIEFS

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

• On July 13, 2021, the inspectors presented the integrated inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.

• On April 16, 2021, the inspectors presented the Radiation Protection inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.

• On April 16, 2021, the inspectors presented the Inservice inspection results to Mr. J. Keenan, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action 4243133 2DG01KB-Y1 East End Bell Oil Leak 12 DPM When Diesel 05/24/2019

Documents Running

4306628 1RH8703B has Evidence of Packing Leak 12/29/2019

4367735 1A RH Pump has Boric Acid Buildup on Pump Seal/Bowl 09/06/2020

4367738 1B RH Pump has Boric Acid Buildup on Pump Seal/Bowl 09/06/2020

4374335 1RH610 Unsat Grease Inspection 10/05/2020

4374466 Boric Acid Residue in 1RH01PA Pump Bowl 10/05/2020

4378052 1B RH Pump Flow Requires IR for Tracking 10/20/2020

22278 2A DG Turbocharger Spindown not be Performed as 05/07/2021

Scheduled

22966 2DG01KA-C, 2A DG Jacket Water Pump is Leaking 05/11/2021

Procedures BwOP CC-E1 Electrical Lineup Unit 1 Operating 8

BwOP CC-M1 Operating Mechanical Lineup Unit 1 18

BwOP DG-E3 Electrical Lineup Unit 2A Diesel Generator 8

BwOP DG-M3 Operating Mechanical Lineup Unit 2A Diesel Generator 15

BwOP FC-M1 Operating Mechanical Lineup Unit 1 10

BwOP RH-6 Placing the RH System in Shutdown Cooling 60

BwOP RH-8 Filling the Reactor Cavity for Refueling 24

BwOP RH-E1 Electrical Lineup Unit 1 Operating 10

BwOP RH-M1 Operating Mechanical Lineup Unit 1 1A RH Train 14

BwOP RH-M2 Operating Mechanical Lineup Unit 1 1B Train 10

BwOP SI-E2 Electrical Lineup Unit 2 Operating 10

BwOP SI-M2 Operating Mechanical Lineup Unit 2 24

71111.05 Fire Plans Pre-Fire Plan 1 Fire Zone 1.1-1; Containment 377'-0" Elevation Unit 1 1

Containment Missile Shield Area

Pre-Fire Plan 6 Fire Zone 1.2-1; Containment 401'-0" Elevation Unit 1 1

Annular Area

Pre-Fire Plan 9 Fire Zone 1.3-1; Containment 426'-0" Elevation Unit 1 2

Containment Upper Area

Pre-Fire Plan 96 Fire Zone 11.1A-0; Auxiliary Building 330' Elevation, Unit 1 2

Auxiliary Building Basement (1A/2A SX)

Inspection Type Designation Description or Title Revision or

Procedure Date

Pre-Fire Plan No. Fire Zone 11.4A-1; Auxiliary Building 383' Elevation, Unit 2 3

137 Auxiliary Feedwater Pump Diesel Room

Pre-Fire Plan No. Fire Zone 5.4-2; Switchgear Area 451' Elevation, Division 22, 1

MEER and Battery Room

Procedures BwAP 1110-1 Fire Protection Program System Requirements 44

BwAP 1110-3 Plant Barrier Impairment Program 39

BwOP PBI-1 Plant Barrier Impairment Program Pre-Evaluated Barrier 4

Matrix

CC-AA-201 Plant Barrier Control Program 13

ER-AA-600-1069 High Risk Fire Area Identification 4

ER-BR-600-1069 Site List of High Risk Fire Areas Braidwood Unit 1 and 0

Unit 2

OP-AA-201-004 Fire Prevention for Hot Work 17

OP-AA-201-008 Pre-Fire Plan Manual 4

OP-AA-201-009 Control of Transient Combustible Material 26

OP-AA-201-012- Operations On-Line Fire Risk Management 4

1001

Pre-Fire Plan No. Fire Zone 1.1-1; Containment 401'-0" Elevation Unit 1 1

Containment Missile Shield Area

71111.08P Corrective Action 4129240 OSP-X 1RC01R NDE Results for 1RV-03-002 Reactor Head 04/20/2018

Documents Weld

272501 Notification of Code Nonconformance for Replacement SGs 08/16/2019

4345873 BA Leak Downstream 1SI023A 05/26/2020

4346974 Leak Found during Robot Inspection of U1 CNTMNT - IMB 05/31/2020

1RC8042B

4391367 1RC8042B Exhibiting a Different Leak Path 12/20/2020

480489 Boric Acid Accumulation Bottom of Pressurizer (Investigate 04/19/2006

Source)

480489 Boric Acid Accumulation Bottom of Pressurizer (Investigate 04/19/2006

Source)

Miscellaneous ASME Weld Data Record, Weld 1 and Weld 4 - I SXA9A 04/11/2021

ASME Weld Data Record, Weld 6-1 and Weld 11-1 - 04/12/2021

1RC8042B

B. Connolly- VT Level II, Certification 01/11/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

R. Kramer - VT Level III, Certification 01/29/2020

J. Jenning - UT Level II, Certification 12/03/2020

B. Knoff - UT Level II, Certification 01/29/2021

J. Simpson - UT Level II, Certification 01/06/2021

WPS 1-1-GTSM-PWHT 5

PQR A-001 10/19/1998

PQR A-002 03/09/1999

PQR 1-50C 01/03/1984

Rod Ticket - Field Welds 1,2,3,4 (WO 04817111-01) 04/11/2021

WPS 8-8-GTSM 6

PQR 1-51A 12/28/1983

PQR 4-51A 09/12/1986

2S Evaluation of BACC Leakage 06/22/2020

(AR 04345873), 1SI023A D/S Adapter and Instrument

Cap- SI PMPS INJECTION HDR TO LOOP 3 COLD LEG

INST ISOL TO 1FT-S1051

2S Evaluation of BACC Leakage (AR 04345861) 06/18/2020

1PS9356A-RC Loop Sample Inside Isolation VLV Assembly,

PS, A Train

Evaluation of BACC Leakage 1RC8042B 07/09/2020

(AR 04346974 & AR 04391367) - RC Loop 1B Equalization

Line Main Isolation VLV

CB1404 Welder Certification Record 10/26/2020

D9350 Welder Certification Record 09/29/2020

EPRI PDQS No. WDI-STD-1165, Revision 3 Addenda 0 01/21/2021

2

NDE Reports 04981252-01 VT-2 Visual Examination - 1 RC-27 and 1 RC-20 04/14/2021

21-MT-11 Magnetic Particle Examination- Welds 1,2,3, and 4 09/11/2021

21-PT-010 Liquid Penetrant Examination- Field Weld# 6-1, Line 04/14/2021

1RC22AB 1-1/2"

21-PT-011 Liquid Penetrant Examination- Field Weld# 11-1, Line 04/14/2021

1RC22AB 1-1/2"

A1R22-UT-001 Ultrasonic Examination- 1RC-16-02 04/10/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

A1R22-UT-002 Ultrasonic Examination- 1RC-35-02 04/10/2021

A1R22-UT-003 Ultrasonic Examination- 1RC-35-04 04/10/2021

A1R22-UT-005 Ultrasonic Examination- 1PZR-01-N3 04/13/2021

A1R22-UT-006 Ultrasonic Examination- 1PZR-01-N2 04/13/2021

A1R22-UT-023 1RV-03 04/16/2021

A1R22-UT-035 Ultrasonic Examination- 1MS-04-37 04/15/2021

A1R22-UT-036 Ultrasonic Examination- 1MS-04-38 04/15/2021

A1R22-UT-037 1FW-04-37 04/16/2021

A1R22-UT-038 Ultrasonic Examination- 1MS-04-34 04/15/2021

A1R22-UT-039 Ultrasonic Examination- 1MS-04-35 04/15/2021

A1R22-UT-040 Ultrasonic Examination- 1MS-04-36 04/15/2021

A1R22-UT-041 Ultrasonic Examination- 1FW-04-35 04/15/2021

A1R22-UT-042 Ultrasonic Examination- 1FW-04-34 04/15/2021

A1R22-UT-043 1SG-05-SGC-02 04/16/2021

A1R22-UT-046 1FW-04-38 04/16/2021

A1R22-VEN-002 1RC01R Top Head BMV 04/15/2021

ANALYSIS LOG 1RV-01-022 (DM) / 1 RV-01-030 (SS) 04/16/2021

1. WN22-01

ANALYSIS LOG 1RV-01-029 (DM) / 1RV-01-037 (SS) 04/16/2021

1. WN338-01

ANALYSIS LOG# 1RV-01-025 (DM) / 1RV-01-033 (SS) 04/16/2021

WN158-01

Procedures ER-AA-335-002 Liquid Penetrant (PT) Examination 12

ER-AA-335-003 Magnetic Particle (MT) Examination 5

ER-AA-335-015- VT-2 Visual Examination in Accordance with ASME 2013 1

2013

ER-AA-335-030 Ultrasonic Examination of Ferritic Piping Welds 5

ER-AA-335-031 Ultrasonic Examination of Austenitic Piping Welds 8

ER-AA-335-034 Manual Ultrasonic Examination of Reactor Pressure Vessel 3

Welds

ER-AA-335-035 Manual Sizing of Ultrasonic Indications in Reactor Pressure 3

Vessel Welds

ER-AA-335-049 Ultrasonic Examination in Accordance with Section V, 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Article 4

ER-AP-331 Boric Acid Corrosion Control (BACC) Program 10

ER-AP-331-1001 Boric Acid Corrosion Control (BACC) Inspection Locations, 11

Implementation, and Inspection Guidelines

ER-AP-331-1002 Boric Acid Corrosion Control Program Identification 11

Screening and Evaluation

ER-AP-335-001 Bare Metal Visual Examination for Nickel Alloy Materials 8

WDI-STD-1165 Automated Ultrasonic Examination of the Remote Inservice 3

Inspection of Reactor Vessel

Nozzle to Safe End, Nozzle to Pipe, and Safe End to Pipe

Welds Using the Athena Phased Array System

71111.11Q Operability TQ-BR-201-0113 Braidwood Training Department Simulator Examination 23

Evaluations Security Actions

Procedures OP-AA-101-111- Operations Standards and Expectations 26

1001

OP-AA-101-113 Operator Fundamentals 14

OP-AA-101-113- 4.0 Crew Critique Guidelines 11

1006

OP-AA-103-102 Watch-Standing Practices 20

OP-AA-103-102- Strategies for Successful Transient Mitigation 2

1001

OP-AA-103-103 Operation of Plant Equipment 1

OP-AA-104-101 Communications 5

OP-AA-111-101 Operating Narrative Logs and Records 17

OP-AA-300 Reactivity Management 14

TQ-AA-10 Systematic Approach to Training Process Description 6

TQ-AA-150 Operator Training Programs 20

TQ-AA-155 Conduct of Simulator Training and Evaluation 11

TQ-AA-201 Examination Security and Administration 18

TQ-AA-306 Simulator Management 10

TQ-BR-201-0113 Braidwood Training Department Simulator Examination 23

Security Actions

71111.12 Corrective Action 1354708 A1R16 (1RC8042B Boric Acid Leakage Refurbish or 04/16/2012

Documents Replace)

Inspection Type Designation Description or Title Revision or

Procedure Date

1355845 1RC8042B will not Close 04/08/2012

24573 OSP-A Boric Acid Dry on Valve 1RC8042B (Clean) 04/09/2018

Engineering 394386 Engineering Review of Flowserve Test Report TAL-20820, 08/28/2013

Changes Revision 2, for a 1.5-Inch ASME Class 1878 Stainless Steel

Y-Pattern Globe Valve for Braidwood Station

Procedures ER-AA-310-1001 Maintenance Rule 18-10 Scoping 0

ER-AA-310-1002 Maintenance Rule Functions Safety Significant 3

Classification

ER-AA-320 Maintenance Rule Implementation per NEI 18-10 0

ER-AA-320-1003 Maintenance Rule 18-10 Failure Definitions 0

ER-AA-320-1004 Maintenance Rule 18-10 Performance Monitoring and 1

Dispositioning Between (a)(1) and (a)(2)

Work Orders 5046086 1RC8042B Replace Valve 04/10/2021

71111.13 Corrective Action 4414349 Pre-Freeze NDE UT Readings Below 87.5% Tmin 04/06/2021

Documents 1SXA9A-6"

4414530 Replacement 1A SX Pump Shaft Scratches/Defects 04/06/2021

4414564 1RC8042D Unable to Close Loop Unable to be Drained 04/06/2021

Drawings M-60, Sheet 2 Reactor Coolant Loop 2 Unit 1 BC

Engineering 388765 Freeze Line on 1RC22AB-1 1/2" to Isolate 1FE-0428 04/18/2012

Changes

Procedures BwMP 3100-094 Removal and Installation of Flood Seal Opening Barriers 20

Work Orders 4934317 Replace 1SX01PA in A1R22 04/08/2021

4969069 1RC8042D Difficult to Operate Replace Valve 04/12/2021

5149593 Unexpected 2-10-C6, Rod Control Urgent Failure, SER 05/05/2021

No. 2165

71111.15 Corrective Action 2530091 Anomaly in Unit 2 Pressurizer Level / VCT Level Trend 07/19/2015

Documents 4417398 14-OSP-X Post-Maintenance Testing: 1RC01BD-B Steam 04/18/2021

Generator Snubber Found Leaking at 60 Drops per Minute

21424 Unexpected 2-10-C6, Rod Control Urgent Failure, SER# 05/04/2021

2165

21660 2-10-C6, Rod Control Urgent Failure, SER# 2165 05/05/2021

21778 Unexpected Alarms 1-10-A5 and 1-14-A1 for OPDT 05/05/2021

23270 Unexpected Annunciator: Ovation System Trouble 05/13/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

23503 Corrective Action to 1TY-0441A3 05/13/2021

23535 Unexpected Alarm 1-14-B5 and 1-4-A3 05/14/2021

24225 2A CV Pump Significantly Weaker than 2B CV Pump 05/18/2021

24510 1C OTDT Rescaling Required 05/19/2021

Procedures 2BwOSR 3.5.5.1 Unit Two RCS Seal Injection Flow Surveillance 14

BwAR 1-10-A5 OPDT High Rod Stop C-4 7

BwAR 1-14-A1 OPDT High Reactor Trip Alert 52

BwOP RP-9 Disabling and Restoring Source Range Nuclear Instruments 4

BwVP 312-6 Reactor Coolant System Temperature Instrumentation Delta 3

T and Tave Normalization

ER-AA-600-1012 Risk Management Documentation 14

OP-AA-106-101- Operational Decision Making Process 22

1006

OP-AA-108-111 Adverse Condition Monitoring and Contingency Planning 15

OP-AA-108-115 Operability Determinations (CM-1) 24

Work Orders 5150129 Unexpected Alarms 1-10-A5 and 1-14-A for OPDT 05/06/2021

71111.18 Procedures ER-AA-569 10 CFR 50.69 Program 4

ER-AA-569-1001 10 CFR 50.69 Active Component Risk Significance Insights 4

ER-AA-569-1002 10 CFR 50.69 Passive Component Categorization 3

ER-AA-569-1003 10 CFR 50.69 Risk Informed Categorization for Structures, 6

Systems, and Components

ER-AA-569-1004 10 CFR 50.69 Alternative Treatment Implementation Process 4

ER-AA-569-1005 Integrated Decision Decision-Making Panel for Risk Informed 6

SSC Categorization Duties and Responsibilities

ER-AA-569-1006 Requirements for Immediate, Interim and Periodic 3

Performance Monitoring Reviews

ER-AA-569-1007 Job Familiarization of 50.69 Project Team and Site 5

Personnel

71111.19 Corrective Action 4417074 1A SX Pump Test Results 04/16/2021

Documents 4418193 17-OSP-A 1B Rod Drive Generator Breaker Trip 04/22/2021

Procedures 1 BwOSR Group A IST Requirements for Unit One Diesel Driven 12

5.5.8.AF-3B Auxiliary Feedwater Pump

1BwOSR 3.7.5.7- Unit One Train B Auxiliary Feedwater Flow Path Operability 6

Inspection Type Designation Description or Title Revision or

Procedure Date

Non-Routine Surveillance (Following Cold Shutdown)

1BwOSR 3.8.1.2- Unit One 1A Diesel Generator Operability Surveillance 49

1BwOSR Comprehensive Inservice Testing (IST) Requirements for 12

5.5.8.CV-8 Unit 1 Charging Pumps and Safety Injection System

Charging Check Valve Stroke Test

1BwOSR Comprehensive Inservice Test (IST) Requirements for 1A 16

5.5.8.SX-6A Essential Service Water Pump (1SX01PA)

BwVS 500-6 Low Power Physics Testing 46

BwVS TRM Low Power Physics Data Interpretation 23

3.1.h.1

ER-AA-330-001 Section XI Pressure Testing 18

Work Orders 1953140 1RD02E Rebuild or Replace Rod Drive Motor-Generator 04/06/2021

Set Motor

4793485 1AF01PB ASME 1BwOSR 5.5.8.AF-3B 04/21/2021

4896029 PMT Leak Check 1AF01AB Luble Oil Cooler 04/21/2021

4977795 Low Power Physics Data Interpretation 04/23/2021

4982132 Train B AF Flowpath Operability Following Cold Shutdown 04/21/2021

4983054 CV Cold Leg Check Valve Test 1BwOSR 5.5.8.CV-8 04/07/2021

4985624 Class 1 System Leakage Test (Ascending Mode 3) 04/22/2021

4985631 Class 2/3 System Leakage Test (Ascending Mode 3) 04/22/2021

4987491 Low Power Physics Test Program with Dynamic Rod Worth 04/23/2021

Measurement

4987492 Moderator Temperature Coefficient Low Power Physics 04/23/2021

Testing

26352 1B AF Pump Function Run (ASME) 04/21/2021

5160533 1A Diesel Generator Operability Monthly 06/21/2021

71111.20 Corrective Action 4413057 APS Electrician Received Electrical Arc Flash Burns 03/31/2021

Documents 4414344 01-OSP-A A1R22 GL 88-05 Minor BACC Results for Mode 3 04/06/2021

Descending

Miscellaneous A1R22 Shutdown Safety Plan 1

BR1C22-08.0 Braidwood 1 Cycle 22 Coastdown Reactivity Plan 03/09/2021

Procedures 1BwGP 100-1 Plant Heat up 38

Inspection Type Designation Description or Title Revision or

Procedure Date

1BwGP 100-2 Plant Start up 47

1BwGP 100-3 Power Ascension 5% to 100% 85

1BwGP 100-4 Power Descension 51

1BwGP 100-5 Plant Shutdown and Cooldown 62

1BwGP 100-6 Refueling Outage 33

1BwOS TRM Unit One Containment Loose Debris Inspection 22

2.5.b.1

BwAP 1450-1 Access to Containment 44

BwGP 100-4 Power Descension 51

BwVS TRM Core Reload Sequence and Verification 23

3.1.h.1

ER-AA-600-1043 Shutdown Risk Management 7

HU-AA-1211 Pre-Job Briefings 14

LS-AA-119 Fatigue Management and Work Hour Rules 15

MA-AA-716-008- Reactor Services: Refuel Floor FME Plan 17

1008

OP-AA-108-108 Unit Restart Review 20

OP-AA-108-110 Evaluation of Special Tests or Evolutions 4

OP-AA-300-1520 Reactivity Management - Fuel Handling, Storage, and 7

Refueling

OU-AA-103 Shutdown Safety Management Program 21 - 22

OU-AA-103-1001 Shutdown Safety Plan Independent Review 4

71111.22 Corrective Action 4413124 1MS016C - Pre A1R22 Testing as Found Outside 03/31/2021

Documents Acceptance Range

4413146 Unexpected Annunciator: 1D-14: Fire Alarm 03/31/2021

4413531 1MS014C - Unsat Testing 04/01/2021

4413543 Unit 1 Trend Main Steam Safety Valves Lift Exceedance - 04/01/2021

A1R22

4413654 1MS015C - Unsat Testing 04/02/2021

4413656 1MS015A - Unsat Testing 04/02/2021

Procedures 1BwOSR 3.6.1.1- Primary Containment Type C Local Leakage Rate Test of 16

Chemical and Volume Control System

1BwOSR 1A Diesel Generator Full Load Rejection and Simulated 17

Inspection Type Designation Description or Title Revision or

Procedure Date

3.8.1.10-1 Safety Injection in Conjunction with Undervoltage During

Load Testing

1BwOSR 1A Diesel Generator Loss of Emergency Safety Features 22

3.8.1.11-1 Bus Voltage with No Safety Injection Signal

1BwOSR Comprehensive Inservice Testing (IST) Requirements for 12

5.5.8.CV-8 Unit 1 Charging Pumps and Safety Injection System

Charging Check Valve Stroke Test

BwMP 3305-003 Main Steam Safety Valve Testing Using Setpoint Verification 9

Device

BwOP DG-1 Diesel Generator Alignment to Standby Condition 31

BwOP DG-11 Diesel Generator Startup and Operation 53

BwOP DG-12 Diesel Generator Shutdown 30

BwOSR 3.8.1.19- 1A Diesel Generator Emergency Core Cooling System 24

Sequencer Surveillance

ER-AA-321 Administrative Requirements for Inservice Testing 13

Work Orders 4803148 1A Diesel Generator 24-Hour Load Test and Emergency 04/20/2021

Core Cooling System Sequencer Surveillance

4817382 1A Diesel Generator Loss of Emergency Safety Features 04/20/2021

Bus Voltage with NO Safety Injection

4836102 1A Diesel Generator Safety Injection Signal Override of Test 04/20/2021

Mode

4983054 OP CV Cold Leg Check Valve Test 1BwOSR 04/07/2021

5.5.8.CV-8

5066993 As Found LLRT 1CV8152 and 1CV8160 1BwOSR 04/09/2021

3.6.1.1-9

5067469 IST - 1MS013s/014s/015s016s/017s 03/31/2021

71124.02 ALARA Plans BW-01-21-00612 Core Barrel ISI and all Associated Work Valve 0

Repairs/Inspections

BW-01-21-00613 Reactor Head Disassembly and Reassembly 0

BW-01-21-00623 Reactor Cavity Decon 0

71124.03 Corrective Action 04254289 0EA01C SCBA Compressor has a Small Leak 06/04/2019

Documents 04263013 Mask Fit not Completed for Licensed Operator 07/10/2019

04370062 Evaluate Need for SCBA Kits in the Unit 1 and Unit 2 09/17/2020

Containment Access Facility

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous MSA SCBA/Firehawk Monthly Inspection 03/2021

Procedures RP-AA-825-101- Operation and use of The MSA Firehawk Self-Contained 0

1001 Breathing Apparatus (SCBA)

RP-AA-870-1003 Testing Portable HEPA Filter Units 6

71124.04 Calibration RP-AA-232-1001 FASTSCAN Calibration Acceptance Criteria 02/24/2021

Records RP-AA-700-1235 PM-12 Calibration Data Sheet 07/08/2020

Corrective Action 04268944 NOS ID 2018 Bioassay Program Periodic Measurement not 08/01/2019

Documents Performed

Radiation RP-AA-220 Intake Investigation Form; 7080 04/22/2020

Surveys RP-AA-220 Intake Investigation Form; 5132 04/22/2020

Self-Assessments PI-AA-126-1001- Radiation Protection Dosimetry and Occupational Dose 10/31/2019

F-01 Assessment

71151 Miscellaneous NRC Performance Indicator Data; Mitigating Systems - 04/01/2020 -

Mitigating System Performance Index for High Pressure 03/31/2021

Injection;

NRC Performance Indicator Data; Mitigating Systems 04/01/2020 -

Safety System Functional Failures 03/31/2021

NRC Performance Indicator Data; Mitigating Systems - 04/01/2020 -

Mitigating System Performance Index for Emergency AC 03/31/2021

Power

71152 Corrective Action 3968314 1MS101C "A" Solenoid Replacement Extent of Condition 01/30/2017

Documents 4130120 OSP-A, 1MS101C will not go Open 04/24/2018

201555 1MS101B Failed to Stroke 12/09/2018

256475 1MS101B would not Open when Demanded from its Control 06/13/2019

Switch

27859 1MS101C Failed to Open when Demanded from its Control 06/07/2021

Switch

Procedures NO-AA-10 Quality Assurance Topical Report (QATR) 96 - 97

PI-AA-120 Issue Identification and Screening Process 11

PI-AA-125 Corrective Action Program (CAP) Procedure 7

PI-AA-125-1001 Root Cause Analysis Manual 6

PI-AA-125-1003 Corrective Action Program Evaluation Manual 6

71153 Corrective Action 4430406 Multiple MCR Alarms Received Due to Adverse Weather 06/20/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 4430440 Indication Lost for 1MS-147A Following Unit 1 Reactor Trip 06/21/2021

4430441 Unit 1 Reactor Trip Load Reject 06/21/2021

4430442 Unexpected Annunciator: 1-4-D5 06/21/2021

4430444 1 A/D MSIV Room Fire Alarm Following Reactor Trip 06/21/2021

4430446 N35 and N36 Appear to be Undercompensated 06/21/2021

4430586 4.0 Critique Unit Reactor Trip Due to Generator Load Reject 06/21/2021

4430895 Need WO Generated for Testing Station Site Grounding 06/22/2021

System

4431283 0VV23C has a Sheared Belt 06/24/2021

4432865 Braidwood Site Ground Testing 07/01/2021

Procedures 1BwGP 110-4T4 Reactor Trip Post Response Guideline 0

OP-AA-106-101- Event Response Guidelines 31

1001

OP-AA-108-108 Unit Restart Review 20

OP-AA-108-114 Post Transient Review 13

Work Orders 1685480 0VV23C Perform Belt Inspection 08/09/2017

5164828 0VV23C has a Sheared Belt 06/24/2021

25