IR 05000456/2020002
| ML20211L708 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/28/2020 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2020002 | |
| Preceding documents: |
|
| Download: ML20211L708 (22) | |
Text
July 28, 2020
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2020002 AND 05000457/2020002
Dear Mr. Hanson:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On July 13, 2020, the NRC inspectors discussed the results of this inspection with Mr. J. 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:
05000456/2020002 and 05000457/2020002
Enterprise Identifier: I-2020-002-0023
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Station
Location:
Braceville, IL
Inspection Dates:
April 01, 2020 to June 30, 2020
Inspectors:
R. Bowen, Illinois Emergency Management Agency
J. Bozga, Senior Reactor Inspector
M. Domke, Reactor Inspector
G. Edwards, Health Physicist
M. Holmberg, Senior Reactor Inspector
D. Kimble, Senior Resident Inspector
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 full power. With the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, the unit remained operating at or near full power for the entire inspection period.
Unit 2 began the inspection period operating at full power. On April 6, 2020, the unit reached the end of the fuel cycle and power coast down operations commenced. On April 20, 2020, the unit was shut down for its planned 21st refueling outage (A2R21). Following completion of refueling and other maintenance activities, the reactor was restarted and taken critical on May 5, 2020, and the main electrical generator was synchronized to the power grid the following day. The unit reached full power operation on May 9, 2020, and with the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, the unit 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 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 and during that time 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 20 through June 27, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial physical alignment verification of the following components and trains:
- (1) The 2B Emergency Diesel Generator (EDG) with the 2A EDG inoperable for testing during the week ending May 2, 2020.
- (2) The 2A EDG with the 2B EDG inoperable for testing during the week ending May 2, 2020.
- (3) The 2A Auxiliary Feedwater (AF) train with the 2B AF train out of service for maintenance during the week ending May 16, 2020.
- (4) The 1B Safety Injection (SI) train with the 1A SI train out of service for maintenance during the week ending May 30, 2020.
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 physical inspections and performing reviews to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) The Unit 2 Containment, Fire Zone 1.1-2, during the week ending April 25, 2020.
- (2) The Unit 2 Containment, Fire Zone 1.2-2, during the week ending April 25, 2020.
- (3) The Unit 2 Containment, Fire Zone 1.3-2, during the week ending May 9, 2020.
- (4) The Unit 1 Auxiliary Building, 383 feet elevation, General Area - North, Fire Zone 11.4-0 North, during the week ending June 13, 2020.
- (5) The Unit 1 Auxiliary Building, 346 feet elevation, 1A Containment Spray Pump Room, Fire Zone 11.2B-1, during the week ending June 20, 2020.
- (6) The 1B EDG and Day Tank Room, 401 feet elevation, Fire Zones 9.1-1 and 9.4-1, during the week ending June 27, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated the readiness and performance of the following elements of the station's heat sink features:
- (1) The 2A EDG lube oil coolers during planned periodic inspections as documented in work orders (WOs) 4794446 and 4794447 during the week ending June 13, 2020.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing the documentation for the following activities from April 20, 2020 to May 1, 2020:
03.01.a - Nondestructive Examination and Welding Activities.
- Volumetric ultrasonic examination of welds 2RC14AA, 2RC14AB, 2RC14AC, 2RC14AD, 2RC-07-09, 2RC-07-16, and 2RC-05-03.
- Bottom mounted instrumentation penetrations on the reactor pressure vessel bottom head were visually examined for all 58 penetrations from 4 quadrants to achieve 100 percent coverage.
- There were no examination records with relevant indications accepted for continued service.
- Pressure boundary welds 3-1 and 6-1 from work order no. 4871866, 2SI16BB Remove Minimum Flow Orifice for Internal Inspection.
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- Visual examination of all 78 upper reactor head penetrations and 1 vent from 4 quadrants to achieve 100 percent coverage per work order 4877009-01.
There were no volumetric or other non-visual exams performed on the upper head.
- There were no reactor head penetration examinations with indications accepted for continued service.
- There were no reactor head penetrations with welded repairs.
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- Boric acid corrective action reports for Boric Acid on 2PS9355B, on 2PS9357B, 2RC014, 2RC001A, and 2RC8042A.
- Boric acid evaluations for 2CV066B, 2SI051, and 2SI8810A.
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- There were no steam generator examinations performed during this inspection on the primary or secondary side.
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 various on-watch Operations shift crew activities, including startup and shutdown activities associated with Unit 2 Refueling Outage A2R21, during the weeks ending April 25 through May 9, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the performance of a complex casualty graded scenario by a crew of licensed plant operators in the facility's simulator on June 23, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance during the following activities to ensure that structures, systems, and components (SSCs) remain capable of performing their intended functions:
- (1) Review of the maintenance effectiveness and performance history for main feedwater check valves 1/2FW079A-D during the weeks ending June 6 through June 20, 2020.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's assessment of risk associated with the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Emergent repairs to Unit 2 Control Rod Drive Mechanism (CRDM) Penetration 39 guide tube alignment funnel as specified in WO 5033582 during the weeks ending April 25, through May 2, 2020.
- (2) Emergent repairs to the 2A EDG as specified in WO 5036351 during the weeks ending May 9 through May 30, 2020.
- (3) Emergent repairs to the 2B EDG as specified in WO 5036665 during the weeks ending May 9 through May 30, 2020.
- (4) Controller tuning for the 1B and 1C Turbine-Driven Main Feedwater Pumps while operating at high power as specified in WO 5044768 during the weeks ending June 20 through June 27, 2020.
- (5) Emergent repairs to the 2A EDG jacket water circulating pump as specified in WO 5055032 during the week ending June 27, 2020.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Evaluation of 2B SI Train operability and functionality following failure to meet all acceptance criteria during full flow testing as documented in Issue Report (IR)
===4337719 during the weeks ending April 25 through May 9, 2020.
- (2) Evaluation of 2SI8853B operability and functionality after failing pressure testing as documented in IR 4338921 during the weeks ending May 2 through May 23, 2020.
- (3) Evaluation of Unit 2 Containment Emergency Sump Suction Valve (2RH01SB)operability and functionality following excessive leakage testing results as documented in IRs 4338522 and 4338772 during the weeks ending May 2 through May 23, 2020.
- (4) Evaluation of 2A EDG operability and functionality associated with the loss of Direct Current Circuit No. 1 as documented in IR 4340079 during the weeks ending May 9 through May 30, 2020.
- (5) Evaluation of main steam safety valve (MSSV) 2MS016A operability following setpoint testing failure as documented in IR 4335846 during the weeks ending May 2 through June 30, 2020.
- (6) Evaluation of MSSV 2MS014B operability following setpoint testing failure as documented in IR 4335997 during the weeks ending May 2 through June 30, 2020.
- (7) Evaluation of MSSV 2MS016C operability following setpoint testing failure as documented in IR 4336005 during the weeks ending May 2 through June 30, 2020.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
The inspectors reviewed and evaluated the following permanent changes to the facility that were enacted on Unit 2:
- (1) Engineering Change (EC) 400436: Westinghouse Ovation' digital upgrade for 7300 Nuclear Steam Supply System (NSSS) Cabinets 2PA05J, 2PA06J, 2PA07J, and 2PA08J during the weeks ending April 11 through May 30, 2020.
- (2) EC 400362: Westinghouse Ovation' Digital Upgrade for Balance of Plant (BOP)
Cabinets 2PA20JA and 2PA20JB during the weeks ending April 11 through May 30, 2020.
- (3) EC 626998: Rod Control (RD) Ovation' Upgrade Multiplexing Logic and Step Counter Logic Adjustment (Unit 2) during the weeks ending April 11 through May 30, 2020.
- (4) EC 405410: Replacement of the 2B Essential Service Water Pump during the weeks ending April 18 through May 30, 2020.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the following post maintenance testing activities to verify system operability and functionality:
- (1) Functional testing of MSSV 2MS017A following setpoint adjustments as set forth in WO 4867041 during the weeks ending April 18 through May 23, 2020.
- (2) Functional testing of MSSV 2MS017B following setpoint adjustments as set forth in WO 4867041 during the weeks ending April 18 through May 23, 2020.
- (3) Functional testing of MSSV 2MS013B following setpoint adjustments as set forth in WO 4867041 during the weeks ending April 18 through May 23, 2020.
- (4) Functional testing of 2B EDG after emergent maintenance as set forth in WO 4836047 during the week ending May 2, 2020.
- (5) Leakage testing of various reactor coolant system high-to-low pressure isolation valves (PIVs) at 800 to 1000 psig as set forth in WO 4861076 during the week ending May 9, 2020.
- (6) Review of modification acceptance testing (MAT) for Westinghouse Ovation' digital upgrade for 7300 NSSS, BOP, and Turbine-Driven Feedwater Pump (TDFWP)cabinets per ECs 400436, 404362, and 404363 (MAT Test - 400436/404362/404363)during the weeks ending May 9 through May 30, 2020.
- (7) Review of power ascension testing for Westinghouse Ovation' digital upgrade for 7300 NSSS, BOP, and TDFWP cabinets per ECs 400436, 404362, and 404363 (SPP-20-002: Unit 2 Ovation Startup Test) during the weeks ending May 9 through May 30, 2020.
- (8) Unit 2 core alignment verification activities following refueling as set forth in WO 4847014-11 during the week ending May 15, 2020.
- (9) Operability and functionality testing for the 1B Containment Spray (CS) Train following completion of a planned maintenance work window as set forth in WO 5032462 during the weeks ending June 20 through June 27, 2020.
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 2 refueling outage A2R21 during the weeks ending April 25 through May 9, 2020.
71111.22 - Surveillance Testing
The inspectors reviewed and evaluated the following surveillance tests or changes to surveillance testing frequency:
Surveillance Tests (other) (IP Section 03.01) (4 Samples)
(1)2BwOSR 3.8.1.2-1: 2A EDG operability surveillance during the week ending April 11, 2020.
(2)1BwOSR 3.6.6.2: Reactor containment fan cooler surveillance during the week ending April 11, 2020.
- (3) A frequency extension for radiation monitor operational surveillance testing during the week ending April 11, 2020.
(4)1BwOSR 3.7.5.4-2: 1B AF Pump surveillance test during the weeks ending May 16 through May 30, 2020.
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Assessment of unidentified reactor coolant system (RCS) leakage rate on Unit 1 as documented in IRs 4344110, 4344858, 4345453, and 4345579 during the weeks ending May 30 through June 20, 2020.
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
(1)2BwOSR 3.6.3.7-1(2): Primary containment Type C local leakage rate tests of containment purge supply and exhaust isolation valves during the weeks ending April 25 through May 2, 2020.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) The inspectors conducted a review of the implementation of the site's emergency plan by a crew of licensed operators during an evaluated emergency scenario in the facility's simulator on June 23,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Instructions to Workers (IP Section 03.02) (1 Partial)
(1)
(Partial) The inspectors evaluated radiological protection-related instructions to plant workers.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2019 - March 31, 2020)
- (2) Unit 2 (April 1, 2019 - March 31, 2020)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (April 1, 2019 - March 31, 2020)
- (2) Unit 2 (April 1, 2019 - March 31, 2020)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (April 1, 2019 - March 31, 2020)
- (2) Unit 2 (April 1, 2019 - March 31, 2020)
71152 - Problem Identification and Resolution
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 that might be indicative of a more significant safety issue during the weeks ending June 27 through July 4, 2020.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of their corrective action program related to the following issue:
- (1) The inspectors performed a detailed review of Issue Report (IR) 4304787; Part 21-Westinghouse Thermal Sleeves and IR 4320102, WEC NSAL-20-1, RVH CRDM Penetration Thermal Sleeve Failure during the weeks ending May 2 through May 9, 2020.
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (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 April 11 through June 27,
INSPECTION RESULTS
Observation: Thermal Sleeves 71152 The sample selected was associated with a 10 CFR Part 21 notification to the NRC (Westinghouse LTR-NRC-19-79, dated December 12, 2019; ADAMS Accession No.
ML19346H873) and additional information on the 10 CFR Part 21 in Nuclear Safety Advisory Letter (NSAL) NSAL-20-1, Reactor Vessel Head Control Rod Drive Mechanism Penetration Thermal Sleeve Cross-Sectional Failure, dated February 14, 2020 (ADAMS Accession No.
ML20063J583). The specific issue was associated with mechanical fatigue and fracture that leads to flange separation of thermal sleeves in the control rod drive mechanism penetration tubes, which could have a safety consequence that was not previously considered. The review for this sample was conducted to evaluate the licensees use of operating experience and ensure that this issue was adequately evaluated for applicability, and applicable lessons learned communicated to appropriate organizations and implemented.
The licensee performed an evaluation of the most recent thermal sleeve wear measurements taken at thermal sleeve penetrations for Braidwood Units 1 and 2 versus the NSAL-20-1 lowering criteria. The largest thermal wear measurement for Braidwood Units 1 and 2 was less than the NSAL 20-1 lowering criteria, and therefore presently considered acceptable for continued operation. No findings or violations were identified.
Observation: Trend in Human Performance Issues 71152 The inspectors performed a review of plant issues, particularly those entered into the licensees corrective action program (CAP), associated with human performance errors over the past six months. During their review, the inspectors noted that there had been several recent issues at the station that had as their predominant cause errors in human performance. These included, but were not limited to:
- Damage caused to the 2B Rod Drive Motor-Generator set when a foreign material exclusion (FME) cover over a vent on the machine was inadvertently left in place during a test run on April 28, 2020, and the cover was subsequently drawn into the machine. This was entered into the licensees CAP as IR 4339238.
- The valve handle for 2CC9493B, the 2B Reactor Coolant Pump Upper Motor Bearing Component Cooling Water Outlet Isolation, was sheared off when the component was inadvertently struck during the Unit 2 A2R21 refuel outage as personnel inside containment were moving other equipment in the area on April 28, 2020. This was entered into the licensees CAP as IR 4339260.
- On May 9,2020, a ventilation fan for the Division 12 Engineered Safety Features (ESF) Electrical Switchgear Room, 1VX01C, was inadvertently tripped during a planned temperature loop controller calibration for another fan in the area, 1VX03C, when the instrument technicians began work on the wrong component. This was entered into the licensees CAP as IR 4342165.
While none of these issues individually rose to the level of being documented as a finding, taken in aggregate the inspectors concluded that they could suggest a generic level of distraction within the licensees workforce. Licensee management also noted this, as well as several similar issues at the licensees other nuclear facilities, and a targeted human performance intervention was undertaken.
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, 2020, the inspectors presented the integrated inspection results to Mr. J. Keenan, Site Vice President and other members of the licensee staff.
- On April 29, 2020, the inspectors presented the Radiation Protection inspection results to Mr. J. Cady, Radiation Protection Manager and other members of the licensee staff.
- On May 1, 2020, the inspectors presented the Inservice Inspection inspection results to Mr. G. Gugle, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Station Response to Grid Capacity Conditions
Procedures
BwOP AF-E2
Electrical Lineup - Unit 2 Operating
BwOP AF-M2
Operating Mechanical Lineup, Auxiliary Feedwater, Unit
BwOP DG-E3
Electrical Lineup - Unit 2 2A Diesel Generator
BwOP DG-E4
Electrical Lineup - Unit 2 2B Diesel Generator
BwOP DG-M3
Operating Mechanical Lineup Unit 2 2A D/G
BwOP DG-M4
Operating Mechanical Lineup Unit 2 2B D/G
BwOP SI-M1
Operating Mechanical Lineup Unit 1
SI-E1
Electrical Lineup - Unit 1 Operating
Fire Plans
Pre-Fire Plan 10
1.3-2; Containment 426' - 0" Elevation, Unit 2
Containment Upper Area
Pre-Fire Plan 105
Fire Zone 11.2B-1; Auxiliary Building 346' Elevation
Containment Spray Pump 1A Room
Pre-Fire Plan 133
Fire Zone 11.4-0 North; Auxiliary Building 383' Unit 1,
Auxiliary Building General Area - North
Pre-Fire Plan 3
Fire Zone 1.1-2; Containment 377' Elevation, Unit 2
Containment Missile Shield
Pre-Fire Plan 4
Fire Zone 1.1-2; Containment 401' - 0" Elevation, Unit 2
Containment Missile Shield Unit 2
Pre-Fire Plan 7
Fire Zone 1.2-2; Containment 377' - 0" Elevation, Unit 2
Annular Area
Pre-Fire Plan 8
Fire Zone 1.2-2; Containment 401' - 0" Elevation, Unit 2
Annular Area
Pre-Fire Plan 88
Fire Zone 9.1-1, 9.4-1; DG 401' Elevation Diesel
Generator Room 1B and Day Tank 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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ER-BR-600-1069
Site List of High-Risk Fire Areas - Braidwood Unit 1 and
Unit 2
Fire Prevention for Hot Work
Fire Protection System Impairment Control
Pre-Fire Plan Manual
Control of Transient Combustible Material
Work Orders
4794446
Emergency Diesel Generator 2A Lube Oil Lower Cooler
Inspection
06/01/2020
4794447
Emergency Diesel Generator 2A Lube Oil Upper Cooler
Inspection
06/01/2020
Corrective Action
Documents
4336361
2-OSP-A Boric Acid on 2PS9355B Regulator
04/17/2020
4336364
2-OSP-A Boric Acid at 2PS9357B Regulator
04/17/2020
4336731
2-OSP-A A2R21 Boric Acid Leak 2RC014 Seat
Leakage
04/20/2020
4336736
2-OSP-A A2R21 Boric Acid Leak - 2RC001A Packing
04/20/2020
4336742
2-OSP-A A2R21 Boric Acid Leak 2RC8042A
04/20/2020
Corrective Action
Documents
Resulting from
Inspection
4338259
NRC Inspector ID Discrepancy BTW the Weld Map and
Weld Rec
04/24/2020
Engineering
Evaluations
2CV066B
Evaluation of BACC Leakage
2/12/2019
2SI051
Evaluation of BACC Leakage
04/12/2019
2SI8810A
Evaluation of BACC Leakage
10/23/2018
NDE Reports
20-UT-011
UT Calibration/Examination
04/22/2020
20-UT-013
UT Calibration/Examination
04/22/2020
UT Calibration/Examination
04/24/2020
2RC01R Bottom Reactor Head Visual Examination
04/21/2020
Bare Metal Visual Examination of Upper Reactor Head
04/24/2020
Procedures
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
1410568
Osp-A 2RC8036A Body/Bonnet has Dry Boron (cln)
10/16/2018
1412965
Dpm Leak from CAP Downstream of Valve
2RH029A
10/27/2018
1451784
Boric Acid on 2CV066B
2/12/2019
4754836
Unit 2 Reactor Vessel Upper Head Bare Metal Visual
10/18/2018
4871866
2SI16BB Remove Minimum Flow Orifice for Internal
Inspection
01/16/2019
71111.11Q Procedures
Operations Standards and Expectations
Operator Fundamentals
4.0 Crew Critique Guidelines
Watch-Standing Practices
Strategies for Successful Transient Mitigation
Operation of Plant Equipment
Communications
Interface Procedure Between BGE/COMED/PECO and
Exelon Generation (Nuclear/Power) for Transmission
Operations
Operating Narrative Logs and Records
Reactivity Management
T!-AA-10
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
0699328
1FW079B Check Valve Further Closed Than Expected
11/14/2007
4165777
1FW079B Check Valve Further Closed Than 1FW079
A, C, and D
08/20/2018
291137
1FW530 Full Open Following Power Ascension
10/25/2019
4346114
1C Steam Generator Level Excursion
05/27/2020
Engineering
Changes
368412
Evaluation of Feedwater Check Valve-FW079 Failure to
Close for Braidwood Unit 1
11/20/2007
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
631749
Westinghouse Field Change Notice for Tuning 1B/1C
Turbine Driven Feedwater Pumps - PROPRIETARY
06/15/2020
Miscellaneous
Adverse Condition Monitoring Plan; Unit 1 Feedwater
Regulating Valve (FRV) Positions
10/25/2019
Procedures
Maintenance Rule Functions - Safety Significant
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 - Scoping
Maintenance Rule 18-10 - Failure Definitions
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Corrective Action
Documents
4337758
Control Rod Drive Shaft Funnel Core Location M12/Pen
Disengaged From Head
04/23/2020
4340361
13OSP-A: Unexpected Alarm - 2B EDG Trouble/Fail to
Start
05/02/2020
Engineering
Changes
619607
Alternate Weld Detail for Control Rod Drive Mechanism
Guide Funnel
05/11/2017
Procedures
ASME Section XI Repair/Replacement Program
VT-2 Visual Examination in Accordance with ASME
2013
Risk Management
On-Line Risk Management
Conduct of Troubleshooting
Protected Equipment Program
On-Line Risk Management and Assessment
Work Orders
5033582
Control Rod Drive Shaft Funnel Core Location M12/Pen
Disengaged From Head
04/25/2020
5036351
Unexpected Alarm - 2A EDG Trouble/Fail to Start
05/04/2020
5036665
Unexpected Alarm - 2B EDG Trouble/Fail to Start
05/02/2020
Corrective Action
Documents
4337719
2C Hot Leg Flow Out of Tolerance Low During
2BwOSR 5.5.8.SI-11
04/22/2020
4338522
07-OSP-X 2SI1881 Can Valve (2RH01SB) - Does Not
Pass LLRT
04/26/2020
4338772
A2R21LL: 2RH01SB Leak Rate Results
04/27/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4338921
09-OSP-A; 2SI8853B Failed As-Found Set Pressure
Test
04/27/2020
4340079
13OSP-A: Unexpected Alarm - 2A EDG Trouble/Fail to
Start
05/01/2020
Engineering
Changes
631543
Temporary Configuration Change - Defeat the 2A EDG
Cooldown Cycle Relay, 4X3A
05/02/2020
Procedures
2BwOS TRM 2.5.c.1
Unit 2 Safety Injection Pump Hot Leg Flow Balance
Safety Injection System Check Valve Stroke Test
2BwOSR 5.5.8.SI-11
Comprehensive Inservice Testing (IST) Requirements
for Unit 2 Safety Injection Pumps and Safety Injection
Check Valve Stroke Test
BwOP DG-11
Diesel Generator Startup and Operation
Lost Parts Evaluations
Administrative Requirements for Inservice Testing
Risk Management Documentation
Risk Assessments of Missed or Deficient Surveillances
Operational Decision-Making Process
Adverse Condition Monitoring and Contingency
Planning
Operability Determinations (CM-1)
Work Orders
5033577-03
Operations Post-Maintenance Testing - 2SI8816C Flow
Balance and Testing
04/28/2020
Corrective Action
Documents
4339535
2SX150B Failed to Open During Backwash
04/29/2020
4339610
Procedure Changes Required per 2B SX Pump IST
Evaluation
04/30/2020
Drawings
405410
Unit 2A/B SX Pump Replacement Alternate Detail
07/12/2016
Engineering
Changes
040362
Westinghouse Ovation' Digital Upgrade for Balance of
Plant (BOP) Cabinets 2PA20JA and 2PA20JB
400436
Westinghouse Ovation' Digital Upgrade For 7300
NSSS Cabinets 2PA05J, 2PA06J, 2PA07J, 2PA08J
(N Outage - Unit 2)
25405
U1 Ovation Post N-Outage Backfit
26998
Rod Control (RD) Ovation' Upgrade Multiplexing Logic
and Step Counter Logic Adjustment (Unit 2)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SPP-20-002
U2 Ovation Startup Test
Work Orders
1845722
EC 400436: Westinghouse Ovation' Digital Upgrade
for 7300 Nuclear Steam Supply System
2/12/2020
4318716
EC 400436: Westinghouse Ovation' Digital Upgrade
for 7300 Nuclear Steam Supply System
04/07/2020
4616851
Install EC 404362: Ovation Balance of Plant (BOP)
Cabinets 2PA20JA and 2PA20JB
04/23/2020
4743474
Temporary Configuration Change - Install/Remove
Temporary Control Panel for 7300 per EC 404450
01/24/2020
4861076
IST-LT-2SI8948A-D/8819A-D-PIV Leak
05/03/2020
4883959
Replace 2SX01PB in A2R21
04/13/2020
4888961
Install EC 626998: Rod Drive Ovation Upgrade
04/23/2020
Procedures
BwMP 3305-003
Main Steam Safety Valve Testing Using Setpoint
Verification Device
Configuration Change Acceptance Testing Criteria
Section XI Pressure Testing
MAT
400436/404362/404363
Westinghouse Ovation' Digital Upgrade Modification
Acceptance Test
MAT 404450
Westinghouse Ovation' Digital Upgrade Modification
Acceptance Test
Inspection/Certification of Portable Pressure Test
Equipment
Core Verification Guideline
Newton Core Gap Data Acquisition for Byron and
Braidwood
On-Line Work Control Process
Work Orders
4836047
2B EDG Pneumatic Component Replacement or
Rebuild
05/11/2020
4844209-01
Physical Reactor Inventory Prior to Installing the
Reactor Head
04/30/2020
4847014-11
Newton Gap Measurements in A2R21
04/29/2020
4861577-01/02
Startup Physics Testing
05/05/2020
4867041-02
Testing of Main Steam Safety Valve 2MS013B
04/15/2020
4867041-17
Testing of Main Steam Safety Valve 2MS017A
04/15/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4867041-18
Testing of Main Steam Safety Valve 2MS017B
04/15/2020
Corrective Action
Documents
4341338
2AFFSO2-6 Not Installed per Design in Mode of
Applicability
05/06/2020
Miscellaneous
BR2C21 08.0
Unit 2 Cycle 21 Coastdown Reactivity Plan
03/25/2020
BR2C21 09.0
Unit 2 Cycle 21 Main Steam Safety Valve and Auxiliary
Feedwater Full Flow Testing Reactivity Plan
04/13/2020
PORC-20-006-02
A2R21 Shutdown Safety Plan
2/28/2020
PORC-20-013
A2R21 Restart Review
05/02/2020
Procedures
2BwGP 100-1
Plant Heatup
2BwGP 100-2
Plant Startup
2BwGP 100-3
Power Ascension 5 Percent to 100 Percent
2BwGP 100-5
Plant Shutdown and Cooldown
2BwOS TRM 2.5.b.1
Unit 2: Containment Loose Debris Inspection
2BwOSR 3.1.8.2
Special Test Exceptions - Reactor Coolant System
Tave During Physics Test Surveillance
2BwOSR 3.1.8.3
Special Test Exceptions - Physics Tests Thermal Power
Hourly Surveillance
2BwOSR 3.1.8.4
Unit 2: Shutdown Margin Verification During Physics
Tests
BwAP 1450-1
Access to Containment
BwVS 500-6
Low Power Physics Test Program
BwVS TRM 3.1.h.1
Core Reload Sequence and Verification
Shutdown Risk Management
Pre-Job Briefings
Fatigue Management and Work Hour Rules
Reactor Services: Refuel Floor FME Plan
Unit Restart Review
Evaluation of Special Tests or Evolutions
Miscellaneous
PORC 20-012-1
Revise the Channel Operational Test (COT) of
Radiation Monitors 0PR32J, 0PR33J, 0PR34J,
1/2AR11J, 1/2AR12J, 0AR55J, 0AR56J From Once
Every 92 to Once Every 18 Months, Using Phased
Implementation
04/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1BwOSR 3.6.6.2
Reactor Containment Fan Cooler Surveillance
1BwOSR 3.7.5.4-2
Unit 1 Diesel Driven Auxiliary Feedwater Pump
Surveillance
2BwOSR 3.6.7-1
Primary Containment Type C Local Leakage Rate Tests
of Containment Purge Supply Isolation Valves
2BwOSR 3.6.7-2
Primary Containment Type C Local Leakage Rate Tests
of Containment Purge Exhaust Isolation Valves
2BwOSR 3.8.1.2-1
Unit Two 2A Diesel Generator Operability Surveillance
BwOP DG-1
Diesel Generator Alignment to Standby Condition
BwOP DG-11
Diesel Generator Startup and Operation
BwOP DG-12
Diesel Generator Shutdown
Work Orders
4842753
Primary Containment Type C LLRT of Containment
Purge Exhaust Isolation Valves
04/24/2020
4848777
U-2 Containment Type C LLRT of Containment Purge
Supply Isolation Valves
04/24/2020
Procedures
Standardized Radiological Emergency Plan
Radiological Emergency Plan Annex for Braidwood
Station
ALARA Plans
BW-02-20-00521
Task 4 2RC8042A Emergent Work
04/22/2020
Corrective Action
Documents
MMD Individual Receives Unplanned Dose Alarm
04/20/2020
Dose Exceeds 25 Percent of ALARA Plan Estimate
BW-02-20-00645
04/29/2020
Level 1 PCE on 2RY45
04/20/2020
Radiation
Surveys
20-071688
Unit 2 Containment Elevation 377' Inside Missile Barrier 04/26/2020
Radiation Work
Permits (RWPs)
BW-02-20-00510
A2R21 Containment/Aux Building Outage Valve Work
with Added Controls
BW-02-20-00521
Task 4 2RC8042A Emergent Work
BW-02-20-00613
Task 1, Reactor Head Disassembly, Reactor Head
Reassembly/Task 2, Conoseal Work, RVLS and O-Ring
Replacement
71151
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Emergency
AC Power
04/2019 -
03/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for High Pressure
Injection
04/2019 -
03/2020
NRC Performance
Indicator Data;
Safety System
Functional Failures
04/2019 - 03/2020
Procedures
Collecting and Reporting of NRC Performance Indicator
Data
Mitigating System Performance Index Data Acquisition
and Reporting
Monthly Data Elements for NRC Safety System
Functional Failures
Corrective Action
Documents
4304787
Part 21-Westinghouse Thermal Sleeves
2/18/2019
20102
WEC NSAL-20-1, RVH CRDM Penetration Thermal
Sleeve Failure
2/21/2020
Engineering
Changes
24381
Review of Westinghouse CRDM Thermal Sleeve Part
24381
Review of Westinghouse CRDM Thermal Sleeve Part
630255
CRDM Thermal Sleeve Lowering to the Acceptance
Criteria in PWROG-16003-P Rev 2 to Determine the
Current Condition of CRDM Thermal Sleeve Wear
Miscellaneous
Nuclear Safety
Advisory Letter (NSAL)-
20-1
Reactor Vessel Head Control Rod Drive Mechanism
Penetration Thermal Sleeve Cross-Sectional Failure
2/14/2020
Procedures
Quality Assurance Topical Report (QATR)
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
5