IR 05000456/2020002

Integrated Inspection Report 05000456/2020002 and 05000457/2020002

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:	ML20056F297 (25 February 2020)
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: NPF-72 and NPF-77 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 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 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.

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)

(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,

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures OP-AA-108-107-1001 Station Response to Grid Capacity Conditions 7

71111.04 Procedures BwOP AF-E2 Electrical Lineup - Unit 2 Operating 11

BwOP AF-M2 Operating Mechanical Lineup, Auxiliary Feedwater, Unit 18

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

BwOP DG-E4 Electrical Lineup - Unit 2 2B Diesel Generator 7

BwOP DG-M3 Operating Mechanical Lineup Unit 2 2A D/G 15

BwOP DG-M4 Operating Mechanical Lineup Unit 2 2B D/G 16

BwOP SI-M1 Operating Mechanical Lineup Unit 1 27

SI-E1 Electrical Lineup - Unit 1 Operating 12

71111.05 Fire Plans Pre-Fire Plan 10 1.3-2; Containment 426' - 0" Elevation, Unit 2 3

Containment Upper Area

Pre-Fire Plan 105 Fire Zone 11.2B-1; Auxiliary Building 346' Elevation 2

Containment Spray Pump 1A Room

Pre-Fire Plan 133 Fire Zone 11.4-0 North; Auxiliary Building 383' Unit 1, 2

Auxiliary Building General Area - North

Pre-Fire Plan 3 Fire Zone 1.1-2; Containment 377' Elevation, Unit 2 1

Containment Missile Shield

Pre-Fire Plan 4 Fire Zone 1.1-2; Containment 401' - 0" Elevation, Unit 2 1

Containment Missile Shield Unit 2

Pre-Fire Plan 7 Fire Zone 1.2-2; Containment 377' - 0" Elevation, Unit 2 2

Annular Area

Pre-Fire Plan 8 Fire Zone 1.2-2; Containment 401' - 0" Elevation, Unit 2 2

Annular Area

Pre-Fire Plan 88 Fire Zone 9.1-1, 9.4-1; DG 401' Elevation Diesel 2

Generator Room 1B and Day Tank Room

Procedures BwAP 1110-1 Fire Protection Program System Requirements 44

BwAP-1110-3 Plant Barrier Impairment Program 38

BwOP PBI-1 Plant Barrier Impairment Program Pre-Evaluated 3

Barrier Matrix

CC-AA-201 Plant Barrier Control Program 12

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

Inspection Type Designation Description or Title Revision or

Procedure Date

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-201-007 Fire Protection System Impairment Control 0

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

OP-AA-201-009 Control of Transient Combustible Material 25

71111.07A Work Orders 4794446 Emergency Diesel Generator 2A Lube Oil Lower Cooler 06/01/2020

Inspection

4794447 Emergency Diesel Generator 2A Lube Oil Upper Cooler 06/01/2020

Inspection

71111.08P Corrective Action 4336361 02-OSP-A Boric Acid on 2PS9355B Regulator 04/17/2020

Documents 4336364 02-OSP-A Boric Acid at 2PS9357B Regulator 04/17/2020

4336731 02-OSP-A A2R21 Boric Acid Leak 2RC014 Seat 04/20/2020

Leakage

4336736 02-OSP-A A2R21 Boric Acid Leak - 2RC001A Packing 04/20/2020

4336742 02-OSP-A A2R21 Boric Acid Leak 2RC8042A 04/20/2020

Corrective Action 4338259 NRC Inspector ID Discrepancy BTW the Weld Map and 04/24/2020

Documents Weld Rec

Resulting from

Inspection

Engineering 2CV066B Evaluation of BACC Leakage 12/12/2019

Evaluations 2SI051 Evaluation of BACC Leakage 04/12/2019

2SI8810A Evaluation of BACC Leakage 10/23/2018

NDE Reports 2020-UT-011 UT Calibration/Examination 04/22/2020

20-UT-013 UT Calibration/Examination 04/22/2020

A2R21-UT-003 UT Calibration/Examination 04/24/2020

A2R21-VEN-001 2RC01R Bottom Reactor Head Visual Examination 04/21/2020

A2R21-VEN-002 Bare Metal Visual Examination of Upper Reactor Head 04/24/2020

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

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

Locations, Implementation and Inspection Guidelines

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

Screening and Evaluation

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 1410568 Osp-A 2RC8036A Body/Bonnet has Dry Boron (cln) 10/16/2018

1412965 12 Dpm Leak from CAP Downstream of Valve 10/27/2018

2RH029A

1451784 Boric Acid on 2CV066B 12/12/2019

4754836 Unit 2 Reactor Vessel Upper Head Bare Metal Visual 10/18/2018

4871866 2SI16BB Remove Minimum Flow Orifice for Internal 01/16/2019

Inspection

71111.11Q Procedures OP-AA-101-111-1001 Operations Standards and Expectations 24

OP-AA-101-113 Operator Fundamentals 14

OP-AA-101-113-1006 4.0 Crew Critique Guidelines 10

OP-AA-103-102 Watch-Standing Practices 19

OP-AA-103-102-1001 Strategies for Successful Transient Mitigation 2

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

OP-AA-104-101 Communications 4

OP-AA-108-107-1002 Interface Procedure Between BGE/COMED/PECO and 12

Exelon Generation (Nuclear/Power) for Transmission

Operations

OP-AA-111-101 Operating Narrative Logs and Records 16

OP-AA-300 Reactivity Management 14

T!-AA-10 Systematic Approach to Training Process Description 6

TQ-AA-150 Operator Training Programs 18

TQ-AA-155 Conduct of Simulator Training and Evaluation 9

TQ-AA-201 Examination Security and Administration 17

TQ-AA-306 Simulator Management 9

TQ-BR-201-0113 Braidwood Training Department Simulator Examination 22

Security Actions

71111.12 Corrective Action 0699328 1FW079B Check Valve Further Closed Than Expected 11/14/2007

Documents 4165777 1FW079B Check Valve Further Closed Than 1FW079 08/20/2018

A, C, and D

291137 1FW530 Full Open Following Power Ascension 10/25/2019

4346114 1C Steam Generator Level Excursion 05/27/2020

Engineering 368412 Evaluation of Feedwater Check Valve-FW079 Failure to 11/20/2007

Changes Close for Braidwood Unit 1

Inspection Type Designation Description or Title Revision or

Procedure Date

631749 Westinghouse Field Change Notice for Tuning 1B/1C 06/15/2020

Turbine Driven Feedwater Pumps - PROPRIETARY

Miscellaneous Adverse Condition Monitoring Plan; Unit 1 Feedwater 10/25/2019

Regulating Valve (FRV) Positions

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

Classification

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

ER-AA-320-1001 Maintenance Rule 18-10 - Scoping 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)

71111.13 Corrective Action 4337758 Control Rod Drive Shaft Funnel Core Location M12/Pen 04/23/2020

Documents 39 Disengaged From Head

4340361 13OSP-A: Unexpected Alarm - 2B EDG Trouble/Fail to 05/02/2020

Start

Engineering 619607 Alternate Weld Detail for Control Rod Drive Mechanism 05/11/2017

Changes Guide Funnel

Procedures ER-AA-330-009 ASME Section XI Repair/Replacement Program 17

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

2013

ER-AA-600 Risk Management 7

ER-AA-600-1042 On-Line Risk Management 11

MA-AA-716-004 Conduct of Troubleshooting 17

OP-AA-108-117 Protected Equipment Program 5

WC-AA-101-1006 On-Line Risk Management and Assessment 3

Work Orders 5033582 Control Rod Drive Shaft Funnel Core Location M12/Pen 04/25/2020

Disengaged From Head

5036351 Unexpected Alarm - 2A EDG Trouble/Fail to Start 05/04/2020

5036665 Unexpected Alarm - 2B EDG Trouble/Fail to Start 05/02/2020

71111.15 Corrective Action 4337719 2C Hot Leg Flow Out of Tolerance Low During 04/22/2020

Documents 2BwOSR 5.5.8.SI-11

4338522 07-OSP-X 2SI1881 Can Valve (2RH01SB) - Does Not 04/26/2020

Pass LLRT

4338772 A2R21LL: 2RH01SB Leak Rate Results 04/27/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

4338921 09-OSP-A; 2SI8853B Failed As-Found Set Pressure 04/27/2020

Test

4340079 13OSP-A: Unexpected Alarm - 2A EDG Trouble/Fail to 05/01/2020

Start

Engineering 631543 Temporary Configuration Change - Defeat the 2A EDG 05/02/2020

Changes Cooldown Cycle Relay, 4X3A

Procedures 2BwOS TRM 2.5.c.1 Unit 2 Safety Injection Pump Hot Leg Flow Balance 2

Safety Injection System Check Valve Stroke Test

2BwOSR 5.5.8.SI-11 Comprehensive Inservice Testing (IST) Requirements 13

for Unit 2 Safety Injection Pumps and Safety Injection

Check Valve Stroke Test

BwOP DG-11 Diesel Generator Startup and Operation 51

ER-AA-2006 Lost Parts Evaluations 14

ER-AA-321 Administrative Requirements for Inservice Testing 13

ER-AA-600-1012 Risk Management Documentation 14

ER-AA-600-1045 Risk Assessments of Missed or Deficient Surveillances 7

OP-AA-106-101-1006 Operational Decision-Making Process 22

OP-AA-108-111 Adverse Condition Monitoring and Contingency 14

Planning

OP-AA-108-115 Operability Determinations (CM-1) 23

Work Orders 5033577-03 Operations Post-Maintenance Testing - 2SI8816C Flow 04/28/2020

Balance and Testing

71111.18 Corrective Action 4339535 2SX150B Failed to Open During Backwash 04/29/2020

Documents 4339610 Procedure Changes Required per 2B SX Pump IST 04/30/2020

Evaluation

Drawings 405410 Unit 2A/B SX Pump Replacement Alternate Detail 07/12/2016

Engineering 040362 Westinghouse Ovation' Digital Upgrade for Balance of 2

Changes Plant (BOP) Cabinets 2PA20JA and 2PA20JB

400436 Westinghouse Ovation' Digital Upgrade For 7300 3

NSSS Cabinets 2PA05J, 2PA06J, 2PA07J, 2PA08J

(N Outage - Unit 2)

25405 U1 Ovation Post N-Outage Backfit 1

26998 Rod Control (RD) Ovation' Upgrade Multiplexing Logic 0

and Step Counter Logic Adjustment (Unit 2)

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures SPP-20-002 U2 Ovation Startup Test 0

Work Orders 1845722 EC 400436: Westinghouse Ovation' Digital Upgrade 02/12/2020

for 7300 Nuclear Steam Supply System

4318716 EC 400436: Westinghouse Ovation' Digital Upgrade 04/07/2020

for 7300 Nuclear Steam Supply System

4616851 Install EC 404362: Ovation Balance of Plant (BOP) 04/23/2020

Cabinets 2PA20JA and 2PA20JB

4743474 Temporary Configuration Change - Install/Remove 01/24/2020

Temporary Control Panel for 7300 per EC 404450

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

71111.19 Procedures BwMP 3305-003 Main Steam Safety Valve Testing Using Setpoint 3

Verification Device

CC-AA-107 Configuration Change Acceptance Testing Criteria 11

ER-AA-330-001 Section XI Pressure Testing 17

MAT Westinghouse Ovation' Digital Upgrade Modification 1

400436/404362/404363 Acceptance Test

MAT 404450 Westinghouse Ovation' Digital Upgrade Modification 1

Acceptance Test

MM-AA-793-044 Inspection/Certification of Portable Pressure Test 5

Equipment

NF-AA-330-1001 Core Verification Guideline 12

OU-AP-230 Newton Core Gap Data Acquisition for Byron and 4

Braidwood

WC-AA-101 On-Line Work Control Process 29

Work Orders 4836047 2B EDG Pneumatic Component Replacement or 05/11/2020

Rebuild

4844209-01 Physical Reactor Inventory Prior to Installing the 04/30/2020

Reactor Head

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 Type Designation Description or Title Revision or

Procedure Date

4867041-18 Testing of Main Steam Safety Valve 2MS017B 04/15/2020

71111.20 Corrective Action 4341338 2AFFSO2-6 Not Installed per Design in Mode of 05/06/2020

Documents Applicability

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 04/13/2020

Feedwater Full Flow Testing Reactivity Plan

PORC-20-006-02 A2R21 Shutdown Safety Plan 02/28/2020

PORC-20-013 A2R21 Restart Review 05/02/2020

Procedures 2BwGP 100-1 Plant Heatup 42

2BwGP 100-2 Plant Startup 38

2BwGP 100-3 Power Ascension 5 Percent to 100 Percent 80

2BwGP 100-5 Plant Shutdown and Cooldown 56

2BwOS TRM 2.5.b.1 Unit 2: Containment Loose Debris Inspection 20

2BwOSR 3.1.8.2 Special Test Exceptions - Reactor Coolant System 1

Tave During Physics Test Surveillance

2BwOSR 3.1.8.3 Special Test Exceptions - Physics Tests Thermal Power 1

Hourly Surveillance

2BwOSR 3.1.8.4 Unit 2: Shutdown Margin Verification During Physics 1

Tests

BwAP 1450-1 Access to Containment 44

BwVS 500-6 Low Power Physics Test Program 46

BwVS TRM 3.1.h.1 Core Reload Sequence and Verification 23

ER-AA-600-1043 Shutdown Risk Management 7

HU-AA-1211 Pre-Job Briefings 14

LS-AA-119 Fatigue Management and Work Hour Rules 14

MA-AA-716-008-1008 Reactor Services: Refuel Floor FME Plan 16

OP-AA-108-108 Unit Restart Review 20

OP-AA-108-110 Evaluation of Special Tests or Evolutions 3

71111.22 Miscellaneous PORC 20-012-1 Revise the Channel Operational Test (COT) of 04/17/2020

Radiation Monitors 0PR32J, 0PR33J, 0PR34J,

1/2AR11J, 1/2AR12J, 0AR55J, 0AR56J From Once

Every 92 to Once Every 18 Months, Using Phased

Implementation

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures 1BwOSR 3.6.6.2 Reactor Containment Fan Cooler Surveillance 31

1BwOSR 3.7.5.4-2 Unit 1 Diesel Driven Auxiliary Feedwater Pump 21

Surveillance

2BwOSR 3.6.7-1 Primary Containment Type C Local Leakage Rate Tests 15

of Containment Purge Supply Isolation Valves

2BwOSR 3.6.7-2 Primary Containment Type C Local Leakage Rate Tests 11

of Containment Purge Exhaust Isolation Valves

2BwOSR 3.8.1.2-1 Unit Two 2A Diesel Generator Operability Surveillance 48

BwOP DG-1 Diesel Generator Alignment to Standby Condition 30

BwOP DG-11 Diesel Generator Startup and Operation 51

BwOP DG-12 Diesel Generator Shutdown 30

Work Orders 4842753 Primary Containment Type C LLRT of Containment 04/24/2020

Purge Exhaust Isolation Valves

4848777 U-2 Containment Type C LLRT of Containment Purge 04/24/2020

Supply Isolation Valves

71114.06 Procedures EP-AA-1000 Standardized Radiological Emergency Plan 33

EP-AA-1001 Radiological Emergency Plan Annex for Braidwood 35

Station

71124.01 ALARA Plans BW-02-20-00521 Task 4 2RC8042A Emergent Work 04/22/2020

Corrective Action AR 04337024 MMD Individual Receives Unplanned Dose Alarm 04/20/2020

Documents AR 04339312 Dose Exceeds 25 Percent of ALARA Plan Estimate 04/29/2020

BW-02-20-00645

AR 4337129 Level 1 PCE on 2RY45 04/20/2020

Radiation 2020-071688 Unit 2 Containment Elevation 377' Inside Missile Barrier 04/26/2020

Surveys

Radiation Work BW-02-20-00510 A2R21 Containment/Aux Building Outage Valve Work 0

Permits (RWPs) with Added Controls

BW-02-20-00521 Task 4 2RC8042A Emergent Work 1

BW-02-20-00613 Task 1, Reactor Head Disassembly, Reactor Head 0

Reassembly/Task 2, Conoseal Work, RVLS and O-Ring

Replacement

71151 Miscellaneous NRC Performance Indicator Data; Mitigating Systems - 04/2019 -

Mitigating System Performance Index for Emergency 03/2020

AC Power

Inspection Type Designation Description or Title Revision or

Procedure Date

NRC Performance Indicator Data; Mitigating Systems - 04/2019 -

Mitigating System Performance Index for High Pressure 03/2020

Injection

NRC Performance 04/2019 - 03/2020

Indicator Data;

Mitigating Systems -

Safety System

Functional Failures

Procedures LS-AA-2001 Collecting and Reporting of NRC Performance Indicator 15

Data

LS-AA-2200 Mitigating System Performance Index Data Acquisition 6

and Reporting

SL-AA-2080 Monthly Data Elements for NRC Safety System 7

Functional Failures

71152 Corrective Action 4304787 Part 21-Westinghouse Thermal Sleeves 12/18/2019

Documents 4320102 WEC NSAL-20-1, RVH CRDM Penetration Thermal 02/21/2020

Sleeve Failure

Engineering 624381 Review of Westinghouse CRDM Thermal Sleeve Part 0

Changes 21

24381 Review of Westinghouse CRDM Thermal Sleeve Part 1

630255 CRDM Thermal Sleeve Lowering to the Acceptance 0

Criteria in PWROG-16003-P Rev 2 to Determine the

Current Condition of CRDM Thermal Sleeve Wear

Miscellaneous Nuclear Safety Reactor Vessel Head Control Rod Drive Mechanism 02/14/2020

Advisory Letter (NSAL)- Penetration Thermal Sleeve Cross-Sectional Failure

20-1

Procedures NO-AA-10 Quality Assurance Topical Report (QATR) 94

PI-AA-120 Issue Identification and Screening Process 10

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

PI-AA-125-1001 Root Cause Analysis Manual 5

PI-AA-125-1003 Corrective Action Program Evaluation Manual 5

20