IR 05000456/2021002
| 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:
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
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.
REACTOR SAFETY
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.
- 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
- 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,
RADIATION SAFETY
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 Notification55320, 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 Operation 71152 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
243133
2DG01KB-Y1 East End Bell Oil Leak 12 DPM When Diesel
Running
05/24/2019
4306628
1RH8703B has Evidence of Packing Leak
2/29/2019
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
Scheduled
05/07/2021
22966
2DG01KA-C, 2A DG Jacket Water Pump is Leaking
05/11/2021
Procedures
BwOP CC-E1
Electrical Lineup Unit 1 Operating
BwOP CC-M1
Operating Mechanical Lineup Unit 1
BwOP DG-E3
Electrical Lineup Unit 2A Diesel Generator
BwOP DG-M3
Operating Mechanical Lineup Unit 2A Diesel Generator
BwOP FC-M1
Operating Mechanical Lineup Unit 1
BwOP RH-6
Placing the RH System in Shutdown Cooling
BwOP RH-8
Filling the Reactor Cavity for Refueling
BwOP RH-E1
Electrical Lineup Unit 1 Operating
BwOP RH-M1
Operating Mechanical Lineup Unit 1 1A RH Train
BwOP RH-M2
Operating Mechanical Lineup Unit 1 1B Train
BwOP SI-E2
Electrical Lineup Unit 2 Operating
BwOP SI-M2
Operating Mechanical Lineup Unit 2
Fire Plans
Pre-Fire Plan 1
Fire Zone 1.1-1; Containment 377'-0" Elevation Unit 1
Containment Missile Shield Area
Pre-Fire Plan 6
Fire Zone 1.2-1; Containment 401'-0" Elevation Unit 1
Annular Area
Pre-Fire Plan 9
Fire Zone 1.3-1; Containment 426'-0" Elevation Unit 1
Containment Upper Area
Pre-Fire Plan 96
Fire Zone 11.1A-0; Auxiliary Building 330' Elevation, Unit 1
Auxiliary Building Basement (1A/2A SX)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pre-Fire Plan No.
137
Fire Zone 11.4A-1; Auxiliary Building 383' Elevation, Unit 2
Auxiliary Feedwater Pump Diesel Room
Pre-Fire Plan No.
Fire Zone 5.4-2; Switchgear Area 451' Elevation, Division 22,
MEER and Battery Room
Procedures
BwAP 1110-1
Fire Protection Program System Requirements
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
Plant Barrier Control Program
High Risk Fire Area Identification
ER-BR-600-1069
Site List of High Risk Fire Areas Braidwood Unit 1 and
Unit 2
Fire Prevention for Hot Work
Pre-Fire Plan Manual
Control of Transient Combustible Material
OP-AA-201-012-
1001
Operations On-Line Fire Risk Management
Pre-Fire Plan No.
Fire Zone 1.1-1; Containment 401'-0" Elevation Unit 1
Containment Missile Shield Area
Corrective Action
Documents
29240
OSP-X 1RC01R NDE Results for 1RV-03-002 Reactor Head
04/20/2018
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
1RC8042B
05/31/2020
4391367
1RC8042B Exhibiting a Different Leak Path
2/20/2020
480489
Boric Acid Accumulation Bottom of Pressurizer (Investigate
Source)
04/19/2006
480489
Boric Acid Accumulation Bottom of Pressurizer (Investigate
Source)
04/19/2006
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 -
1RC8042B
04/12/2021
- B. Connolly-VT Level II, Certification
01/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
- R. Kramer - VT Level III, Certification
01/29/2020
- J. Jenning - UT Level II, Certification
2/03/2020
- B. Knoff - UT Level II, Certification
01/29/2021
- J. Simpson - UT Level II, Certification
01/06/2021
WPS 1-1-GTSM-PWHT
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
PQR 1-51A
2/28/1983
PQR 4-51A
09/12/1986
2S Evaluation of BACC Leakage
(AR 04345873), 1SI023A D/S Adapter and Instrument
Cap-SI PMPS INJECTION HDR TO LOOP 3 COLD LEG
INST ISOL TO 1FT-S1051
06/22/2020
2S Evaluation of BACC Leakage (AR 04345861)
1PS9356A-RC Loop Sample Inside Isolation VLV Assembly,
PS, A Train
06/18/2020
Evaluation of BACC Leakage 1RC8042B
(AR 04346974 & AR 04391367) - RC Loop 1B Equalization
Line Main Isolation VLV
07/09/2020
CB1404
Welder Certification Record
10/26/2020
D9350
Welder Certification Record
09/29/2020
EPRI PDQS No.
2
WDI-STD-1165, Revision 3 Addenda 0
01/21/2021
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
1RC22AB 1-1/2"
04/14/2021
21-PT-011
Liquid Penetrant Examination-Field Weld# 11-1, Line
1RC22AB 1-1/2"
04/14/2021
Ultrasonic Examination-1RC-16-02
04/10/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Ultrasonic Examination-1RC-35-02
04/10/2021
Ultrasonic Examination-1RC-35-04
04/10/2021
Ultrasonic Examination-1PZR-01-N3
04/13/2021
Ultrasonic Examination-1PZR-01-N2
04/13/2021
1RV-03
04/16/2021
Ultrasonic Examination-1MS-04-37
04/15/2021
Ultrasonic Examination-1MS-04-38
04/15/2021
1FW-04-37
04/16/2021
Ultrasonic Examination-1MS-04-34
04/15/2021
Ultrasonic Examination-1MS-04-35
04/15/2021
Ultrasonic Examination-1MS-04-36
04/15/2021
Ultrasonic Examination-1FW-04-35
04/15/2021
Ultrasonic Examination-1FW-04-34
04/15/2021
1SG-05-SGC-02
04/16/2021
1FW-04-38
04/16/2021
1RC01R Top Head BMV
04/15/2021
ANALYSIS LOG
- WN22-01
1RV-01-022 (DM) / 1 RV-01-030 (SS)
04/16/2021
ANALYSIS LOG
- WN338-01
1RV-01-029 (DM) / 1RV-01-037 (SS)
04/16/2021
ANALYSIS LOG#
WN158-01
1RV-01-025 (DM) / 1RV-01-033 (SS)
04/16/2021
Procedures
Liquid Penetrant (PT) Examination
Magnetic Particle (MT) Examination
ER-AA-335-015-
2013
VT-2 Visual Examination in Accordance with ASME 2013
Ultrasonic Examination of Ferritic Piping Welds
Ultrasonic Examination of Austenitic Piping Welds
Manual Ultrasonic Examination of Reactor Pressure Vessel
Manual Sizing of Ultrasonic Indications in Reactor Pressure
Vessel Welds
Ultrasonic Examination in Accordance with Section V,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Article 4
Boric Acid Corrosion Control (BACC) Program
Boric Acid Corrosion Control (BACC) Inspection Locations,
Implementation, and Inspection Guidelines
Boric Acid Corrosion Control Program Identification
Screening and Evaluation
Bare Metal Visual Examination for Nickel Alloy Materials
WDI-STD-1165
Automated Ultrasonic Examination of the Remote Inservice
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
Evaluations
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
Procedures
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
Watch-Standing Practices
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
Operation of Plant Equipment
Communications
Operating Narrative Logs and Records
Reactivity Management
Systematic Approach to Training Process Description
Operator Training Programs
Conduct of Simulator Training and Evaluation
Examination Security and Administration
Simulator Management
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
Corrective Action
Documents
1354708
A1R16 (1RC8042B Boric Acid Leakage Refurbish or
Replace)
04/16/2012
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1355845
1RC8042B will not Close
04/08/2012
24573
OSP-A Boric Acid Dry on Valve 1RC8042B (Clean)
04/09/2018
Engineering
Changes
394386
Engineering Review of Flowserve Test Report TAL-20820,
Revision 2, for a 1.5-Inch ASME Class 1878 Stainless Steel
Y-Pattern Globe Valve for Braidwood Station
08/28/2013
Procedures
Maintenance Rule 18-10 Scoping
Maintenance Rule Functions Safety Significant
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 Failure Definitions
Maintenance Rule 18-10 Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Work Orders
5046086
1RC8042B Replace Valve
04/10/2021
Corrective Action
Documents
4414349
Pre-Freeze NDE UT Readings Below 87.5% Tmin
04/06/2021
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
Engineering
Changes
388765
Freeze Line on 1RC22AB-1 1/2" to Isolate 1FE-0428
04/18/2012
Procedures
BwMP 3100-094
Removal and Installation of Flood Seal Opening Barriers
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
No. 2165
05/05/2021
Corrective Action
Documents
2530091
Anomaly in Unit 2 Pressurizer Level / VCT Level Trend
07/19/2015
4417398
14-OSP-X Post-Maintenance Testing: 1RC01BD-B Steam
Generator Snubber Found Leaking at 60 Drops per Minute
04/18/2021
21424
Unexpected 2-10-C6, Rod Control Urgent Failure, SER#
2165
05/04/2021
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
Procedure
Type
Designation
Description or Title
Revision or
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
BwAR 1-10-A5
OPDT High Rod Stop C-4
BwAR 1-14-A1
OPDT High Reactor Trip Alert
BwOP RP-9
Disabling and Restoring Source Range Nuclear Instruments
BwVP 312-6
Reactor Coolant System Temperature Instrumentation Delta
T and Tave Normalization
Risk Management Documentation
OP-AA-106-101-
1006
Operational Decision Making Process
Adverse Condition Monitoring and Contingency Planning
Operability Determinations (CM-1)
Work Orders
5150129
Unexpected Alarms 1-10-A5 and 1-14-A for OPDT
05/06/2021
Procedures
CFR 50.69 Program
CFR 50.69 Active Component Risk Significance Insights
CFR 50.69 Passive Component Categorization
CFR 50.69 Risk Informed Categorization for Structures,
Systems, and Components
CFR 50.69 Alternative Treatment Implementation Process 4
Integrated Decision Decision-Making Panel for Risk Informed
SSC Categorization Duties and Responsibilities
Requirements for Immediate, Interim and Periodic
Performance Monitoring Reviews
Job Familiarization of 50.69 Project Team and Site
Personnel
Corrective Action
Documents
4417074
1A SX Pump Test Results
04/16/2021
4418193
17-OSP-A 1B Rod Drive Generator Breaker Trip
04/22/2021
Procedures
BwOSR
5.5.8.AF-3B
Group A IST Requirements for Unit One Diesel Driven
Auxiliary Feedwater Pump
1BwOSR 3.7.5.7-
Unit One Train B Auxiliary Feedwater Flow Path Operability
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Non-Routine Surveillance (Following Cold Shutdown)
1BwOSR 3.8.1.2-
Unit One 1A Diesel Generator Operability Surveillance
1BwOSR
5.5.8.CV-8
Comprehensive Inservice Testing (IST) Requirements for
Unit 1 Charging Pumps and Safety Injection System
Charging Check Valve Stroke Test
1BwOSR
5.5.8.SX-6A
Comprehensive Inservice Test (IST) Requirements for 1A
Essential Service Water Pump (1SX01PA)
BwVS 500-6
Low Power Physics Testing
BwVS TRM
3.1.h.1
Low Power Physics Data Interpretation
Section XI Pressure Testing
Work Orders
1953140
1RD02E Rebuild or Replace Rod Drive Motor-Generator
Set Motor
04/06/2021
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
Measurement
04/23/2021
4987492
Moderator Temperature Coefficient Low Power Physics
Testing
04/23/2021
26352
1B AF Pump Function Run (ASME)
04/21/2021
5160533
1A Diesel Generator Operability Monthly
06/21/2021
Corrective Action
Documents
4413057
APS Electrician Received Electrical Arc Flash Burns
03/31/2021
4414344
01-OSP-A A1R22 GL 88-05 Minor BACC Results for Mode 3
Descending
04/06/2021
Miscellaneous
A1R22 Shutdown Safety Plan
BR1C22-08.0
Braidwood 1 Cycle 22 Coastdown Reactivity Plan
03/09/2021
Procedures
1BwGP 100-1
Plant Heat up
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1BwGP 100-2
Plant Start up
1BwGP 100-3
Power Ascension 5% to 100%
1BwGP 100-4
Power Descension
1BwGP 100-5
Plant Shutdown and Cooldown
1BwGP 100-6
Refueling Outage
1BwOS TRM
2.5.b.1
Unit One Containment Loose Debris Inspection
BwAP 1450-1
Access to Containment
BwGP 100-4
Power Descension
BwVS TRM
3.1.h.1
Core Reload Sequence and Verification
Shutdown Risk Management
Pre-Job Briefings
Fatigue Management and Work Hour Rules
MA-AA-716-008-
1008
Reactor Services: Refuel Floor FME Plan
Unit Restart Review
Evaluation of Special Tests or Evolutions
Reactivity Management - Fuel Handling, Storage, and
Refueling
Shutdown Safety Management Program
- 22
Shutdown Safety Plan Independent Review
Corrective Action
Documents
4413124
1MS016C - Pre A1R22 Testing as Found Outside
Acceptance Range
03/31/2021
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 -
A1R22
04/01/2021
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
Chemical and Volume Control System
1BwOSR
1A Diesel Generator Full Load Rejection and Simulated
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3.8.1.10-1
Safety Injection in Conjunction with Undervoltage During
Load Testing
1BwOSR
3.8.1.11-1
1A Diesel Generator Loss of Emergency Safety Features
Bus Voltage with No Safety Injection Signal
1BwOSR
5.5.8.CV-8
Comprehensive Inservice Testing (IST) Requirements for
Unit 1 Charging Pumps and Safety Injection System
Charging Check Valve Stroke Test
BwMP 3305-003
Main Steam Safety Valve Testing Using Setpoint Verification
Device
BwOP DG-1
Diesel Generator Alignment to Standby Condition
BwOP DG-11
Diesel Generator Startup and Operation
BwOP DG-12
Diesel Generator Shutdown
BwOSR 3.8.1.19-
1A Diesel Generator Emergency Core Cooling System
Sequencer Surveillance
Administrative Requirements for Inservice Testing
Work Orders
4803148
1A Diesel Generator 24-Hour Load Test and Emergency
Core Cooling System Sequencer Surveillance
04/20/2021
4817382
1A Diesel Generator Loss of Emergency Safety Features
Bus Voltage with NO Safety Injection
04/20/2021
4836102
1A Diesel Generator Safety Injection Signal Override of Test
Mode
04/20/2021
4983054
OP CV Cold Leg Check Valve Test 1BwOSR
5.5.8.CV-8
04/07/2021
5066993
As Found LLRT 1CV8152 and 1CV8160 1BwOSR
3.6.1.1-9
04/09/2021
5067469
IST - 1MS013s/014s/015s016s/017s
03/31/2021
ALARA Plans
BW-01-21-00612 Core Barrel ISI and all Associated Work Valve
Repairs/Inspections
BW-01-21-00613
Reactor Head Disassembly and Reassembly
BW-01-21-00623
Reactor Cavity Decon
Corrective Action
Documents
254289
0EA01C SCBA Compressor has a Small Leak
06/04/2019
263013
Mask Fit not Completed for Licensed Operator
07/10/2019
04370062
Evaluate Need for SCBA Kits in the Unit 1 and Unit 2
Containment Access Facility
09/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
MSA SCBA/Firehawk Monthly Inspection
03/2021
Procedures
RP-AA-825-101-
1001
Operation and use of The MSA Firehawk Self-Contained
Breathing Apparatus (SCBA)
Testing Portable HEPA Filter Units
Calibration
Records
FASTSCAN Calibration Acceptance Criteria
2/24/2021
PM-12 Calibration Data Sheet
07/08/2020
Corrective Action
Documents
268944
NOS ID 2018 Bioassay Program Periodic Measurement not
Performed
08/01/2019
Radiation
Surveys
Intake Investigation Form; 7080
04/22/2020
Intake Investigation Form; 5132
04/22/2020
Self-Assessments PI-AA-126-1001-
F-01
Radiation Protection Dosimetry and Occupational Dose
Assessment
10/31/2019
71151
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for High Pressure
Injection;
04/01/2020 -
03/31/2021
NRC Performance Indicator Data; Mitigating Systems
Safety System Functional Failures
04/01/2020 -
03/31/2021
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Emergency AC
Power
04/01/2020 -
03/31/2021
Corrective Action
Documents
3968314
1MS101C "A" Solenoid Replacement Extent of Condition
01/30/2017
4130120
OSP-A, 1MS101C will not go Open
04/24/2018
201555
1MS101B Failed to Stroke
2/09/2018
256475
1MS101B would not Open when Demanded from its Control
Switch
06/13/2019
27859
1MS101C Failed to Open when Demanded from its Control
Switch
06/07/2021
Procedures
Quality Assurance Topical Report (QATR)
- 97
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
Corrective Action
4430406
Multiple MCR Alarms Received Due to Adverse Weather
06/20/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
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
System
06/22/2021
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
OP-AA-106-101-
1001
Event Response Guidelines
Unit Restart Review
Post Transient Review
Work Orders
1685480
0VV23C Perform Belt Inspection
08/09/2017
5164828
0VV23C has a Sheared Belt
06/24/2021