IR 05000456/2022002

Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001

ML22206A235
Person / Time
Site:	Braidwood
Issue date:	07/26/2022
From:	Hironori Peterson Region 3 Branch 3
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
References
IR 2022002
Download: ML22206A235 (24)

Text

July 26, 2022

SUBJECT:

BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2022002; 05000457/2022002; AND 07200073/2022001

Dear Mr. Rhoades:

On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On July 15, 2022, the NRC inspectors discussed the results of this inspection with Mr. G. Gugle, 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, Signed by Peterson, Hironori on 07/26/22 Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000456; 05000457; and 07200073 License Nos. NPF-72 and NPF-77

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000456; 05000457; and 07200073 License Numbers: NPF-72 and NPF-77 Report Numbers: 05000456/2022002; 05000457/2022002; and 07200073/2022001 Enterprise Identifier: I-2022-002-0044 and I-2022-001-0100 Licensee: Constellation Energy Generation, LLC Facility: Braidwood Station Location: Braceville, IL Inspection Dates: April 01, 2022 to June 30, 2022 Inspectors: R. Bowen, Illinois Emergency Management Agency A. Demeter, Acting Resident Inspector G. Edwards, Health Physicist D. Kimble, Senior Resident Inspector J. Masse, Reactor Engineer 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 and Unit 2 began the inspection period operating at full power. With the exception of short duration reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, both units remained operating at or near full power for the entire 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated the station's offsite and alternate alternating current (AC)power systems for summer readiness and the onset of hot weather during the weeks ending May 21 through June 4, 2022.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

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

(1) The 1B Emergency Diesel Generator (EDG) during 1A EDG maintenance during the week ending April 16, 2022

(2) The 2B Residual Heat Removal (RH) Train during 2A RH Train maintenance during the week ending May 5, 2022

(3) Unit 1 and Unit 2, Division 1, direct current (DC) power while protected during an extended Unit 1 Station Auxiliary Transformer (SAT) maintenance window during the week ending May 14, 2022

(4) Unit 1 EDGs while protected during an extended Unit 1 SAT maintenance window during the week ending May 14,2022

(5) The 2B Auxiliary Feedwater (AF) Train while protected during an extended Unit 1 SAT maintenance window during the week ending May 14, 2022

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)

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:

Unit 1 power maneuvering in response to the system transmission dispatcher, during the week ending April 30, 2022.

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 June 11, 2022.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Maintenance effectiveness review associated with leakage from the Unit 1 Charging and Letdown Regenerative Heat Exchanger Return to the Reactor Coolant System (RCS) Manual Isolation Valve (1CV-8321A) during the weeks ending April 23 through June 25, 2022.

(2) Maintenance effectiveness review associated with EDG local annunciator panel power supplies during the week ending April 23, 2022.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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 emergent work associated with the 2B EDG annunciator panel, as documented in Issue Report (IR) 4490289 during the week ending April 9, 2022.

(2) Evaluation of the planned work associated with 1A EDG, as documented in Work Order (WO) 4901183 during the week ending April 16, 2022.

(3) Evaluation of the emergency activities associated with a leak from a welded joint on the Unit 0 Component Cooling (CC) Heat Exchanger Essential Service Water (SX)

Outlet, as documented in IR 4494801 and WO 5252064 during the weeks ending April 23 through April 30, 2022.

(4) Evaluation of the emergent activities associated with the loss of local alarm annunciators for the 2A EDG, as documented in IR 4493589 and 5249849 during the week ending April 23, 2022.

(5) Evaluation of the work associated with the Unit 1 SAT maintenance window utilizing a planned Technical Specification Risk-Informed Completion Time (TS RICT), as documented in multiple WOs during the week ending May 14, 2022.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) Evaluation of the operability of the 1B EDG following identification of a crack in the jacket water cooling manifold, as documented in IR 4492197 during the week ending April 16, 2022.

(2) Evaluation of the functionality of the Unit 2 Rod Drive System following identification of a degraded power supply, as documented in IR 4471553 during the week ending May 28, 2022.

(3) Evaluation of the operability of the Unit 0 CC Heat Exchanger following identification of a leak through a welded joint on the SX outlet of the heat exchanger, as documented in IR 4494801 during the week ending June 4, 2022.

(4) Evaluation of the operability of the 0B Control Room Chiller (VC) following identification of a degraded chiller oil level, as documented in IR 4505042 during the weeks ending June 25 through June 30, 2022.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary configuration change on Unit 2:

(1) A temporary plant modification per Engineering Change (EC) 635793: Install Temporary Power Supply in 2RD033, during the weeks ending May 21 through May 28, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (1 Sample)

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

(1) Non-destructive testing on the SX side of the Unit 0 CC Heat Exchanger following analysis and evaluation of a leak through a welded joint, as documented in WO 5253243 during the week ending May 21, 2022

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities:

Surveillance Tests (other) (IP Section 03.01)

(1) BwISR 3.3.1.6-004: Quarterly Excore Power Range N44 Axial Flux/7300 Delta Flux Penalty Calibration, as documented in WO 5242877 during the weeks ending

June 11 through June 18, 2022 FLEX Testing (IP Section 03.02) (1 Sample)

(1) 0BwOS FX-12: FLEX Pump Full Flow Test Surveillance, as documented in WOs 5011598 and 5013180 during the weeks ending June 18 through June 25, 2022

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)

The inspectors evaluated site's emergency plan by observing the following emergency response organization (ERO) activities:

(1) A site-wide emergency preparedness drill that resulted in a simulated General Emergency event classification on May 18, 2022

(2) A site-wide emergency preparedness drill that resulted in a simulated General Emergency event classification on June 1,

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) Fuel Handling Building ventilation systems

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

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

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

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

71124.04 - Occupational Dose Assessment

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

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

External Dosimetry (IP Section 03.02) (1 Sample)

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

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Internal dose assessment conducted for an individual reporting onsite that had previously reported having an intake at another facility conducted on October 20, 2021

(2) Internal dose assessment conducted for an individual who was hanging shielding during a valve repair on February 9, 2021

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

The inspectors evaluated the following special dosimetric situations:

(1) Dose assessment for a declared pregnant worker in 2021

(2) Dose assessment for a declared pregnant worker in 2022

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (5 Samples)

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

(1) Area Radiation Monitors in auxiliary building

(2) Area Radiation Monitors in the fuel handling building

(3) Friskers used at the exit to the auxiliary building

(4) Portable ion chambers stored ready for use and/or during use at the Radiation Protection checkpoint at the auxiliary building entrance

(5) Portable ion chambers stored ready for use and/or during use in the Radiation Protection instrument room in the auxiliary building

Calibration and Testing Program (IP Section 03.02) (10 Samples)

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

(1) Thermo Scientific PM12; SN #12084

(2) Bicron RSO-50E; SN #C613F

(3) Thermo Scientific SAM12; SN #235A

(4) Mirion Telepole II; SN #0019520

(5) Mirion Argos 5; SN #1011-279

(6) Ludlum Model 30; SN #26144

(7) Ludlum Model 12-4; SN #336338

(8) Thermo Scientific PM12; SN #12060

(9) Thermo Scientific PM12; SN #12082

(10) Mirion RDS-31; SN #2B.106 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

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

(1) Auxiliary building ventilation stack effluent stack monitor, 1PRJ28

(2) Station blowdown line liquid effluent radiation monitor, 0R-PR010

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 02.04) ===

(1) Unit 1 (April 1, 2021 - March 31, 2022)

(2) Unit 2 (April 1, 2021 - March 31, 2022)

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 (April 1, 2021 - March 31, 2022)

(2) Unit 2 (April 1, 2021 - March 31, 2022)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (April 1, 2021 - March 31, 2022)

(2) Unit 2 (April 1, 2021 - March 31, 2022)

71152A - Annual Follow-Up Problem Identification and Resolution Annual Follow-Up of Selected Issues (Section 03.03)

The inspectors conducted an in-depth review of the licensees implementation of the corrective action program (CAP) related to the following issue:

(1) Review and assessment of the station's corrective actions from a Unit 2 configuration control event where a pressure test signal was applied to the incorrect instrument loop, as documented in IR 4474052 during the weeks ending April 2 through June 30, 2022.

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors conducted a semiannual review of the licensees CAP for potential adverse trends that might be indicative of a more significant safety concern during the weeks ending June 4 through June 30, 2022. A specific trend related to Reactor Vessel Level Indication System (RVLIS) issues is documented in the Results Section of this report.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855 - Operation of an ISFSI Operation of an ISFSI

(1) The inspectors assessed the licensees Independent Spent Fuel Storage Installation (ISFSI) cask loading activities from May 16 through May 20, 2022. Specifically, the inspectors observed the following activities during the loading of multi-purpose canister (MPC) No. 676:

• heavy lift of the loaded transfer cask (HI-TRAC) from the spent fuel pool to the cask processing area

• closure welding and non-destructive evaluations

• canister processing including blowdown and forced helium dehydration

• stack-up and download of the MPC from the HI-TRAC into the storage cask (HI-STORM)

• radiological field surveys The inspectors performed walkdowns of the ISFSI pad, including walkdowns of the ISFSI haul path.

The inspectors evaluated the following:

• spent fuel selected for loading into dry cask storage during this loading campaign

• selected corrective action program documents

• selected 72.48 screenings and evaluations

INSPECTION RESULTS

Observation: Test Signal Inadvertently Applied to the Incorrect Instrument Loop 71152A The inspectors performed a detailed review of IR 4474052, Level 3 Configuration Control:

Incorrect Connection of Test Equipment. The issue involved Instrument Maintenance Department (IMD) calibration procedure BwIP 2P-0120, Calibration of Charging Header Pressure Loop 2P-0120 (CV), which was performed under Work Order (WO) 5063738, 2P-0120 Charging Header Pressure Loop. On January 26, 2022, IMD technicians performing this calibration activity were prompted to change out their test signal equipment partway through the procedure due to a low battery indication. Despite the use of robust barriers within the applicable 2PA06J instrumentation cabinet intended to prevent such an error, the IMD technicians connected the replacement test signal equipment to test connection points associated with the Unit 2 Volume Control Tank (VCT) pressure instrument loop, vice the intended 2P-0120 Charging Header Pressure instrument loop. When the test signal was subsequently applied, Unit 2 operators in the main control room were forced to respond to invalid VCT pressure indications and took steps to stabilize VCT pressure.

The inspectors chose this issue for an in-depth review of the licensees actions within their corrective action program (CAP) because of the inherent risk associated with wrong unit /

wrong component manipulations. While in this particular case the wrong component error did not result in any significant adverse impact to the applicable unit, such an error could have resulted in a significant plant transient or unintended automatic equipment actuation.

Consequently, for this detailed Problem Identification and Resolution inspection sample, the inspectors focused on assessment of the licensees corrective actions taken both for this specific error, as well as those targeted at the more generic issue of addressing potential wrong unit / wrong component errors.

The inspectors determined that the erroneous connection of the IMD test signal equipment to test connection points associated with the Unit 2 VCT pressure instrument loop, vice the intended 2P-0120 Charging Header Pressure instrument loop on January 26, 2022, had constituted a violation of the requirements of TS 5.4.1(a), which requires that written procedures be established, implemented, and maintained for the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. In this case, Section 8.a of Regulatory Guide 1.33, Revision 2, Appendix A, February 1978, contains the requirement for procedures associated with instrument calibrations, and licensee procedure BwIP 2P-0120, Calibration of Charging Header Pressure Loop 2P-0120 (CV),

Revision 1, is an applicable procedure. Section 4.1, Test Setup, of this procedure directs that the IMD test equipment is to be connected to Terminals TBF-7 and TBF-8 in Cabinet 2PA06J to facilitate calibration of the Charging Header Pressure Loop 2P-0120. Contrary to these instructions, the IMD test signal equipment was connected to Terminals TBF-1 and TBF-2 in Cabinet 2PA06J. However, because there were no safety consequences associated with this event, the inspectors concluded that the error had not adversely affected the Initiating Events Cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. As a result, the issue was determined to be a violation of minor significance that was not subject to formal actions per Section 2.3.1 of the NRC Enforcement Policy.

The inspectors did not identify any issues with the licensees CAP actions taken. The licensees formal CAP evaluation revealed that human performance failures had occurred at multiple times during the calibration. Subsequent interviews performed with station supervisors and technicians revealed that multiple interpretations of standards and expectations existed with respect to the use of several human performance tools. Multiple corrective actions targeting this aspect of the event were implemented by the licensee; these included the reinforcement of standards and expectations by plant management with shop superintendents regarding the use of human performance tools, peer-to-peer coaching, and supervisory oversight in the field.

No findings or violations of NRC requirements of more than minor safety significance were identified by the inspectors in the course of this review.

Observation: Trend in Reactor Vessel Level Indication System (RVLIS) Issues 71152S 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 an adverse trend involving the performance of the Reactor Vessel Level Indication System (RVLIS). The majority of issues were on Unit 1, but the inspectors noted that the trend was not exclusive to only that unit. Specific CAP entries reviewed by the inspectors included, but were not limited to:

- IR 4442055; 1-9-D6 - Unexpected Main Control Room Alarm - RVLIS Sensor Uncovered.

- IR 4442887; 1-9-D6 - Unexpected Main Control Room Alarm - RVLIS Sensor Uncovered.

- IR 4450389; Unexpected Main Control Room Alarm - RVLIS Sensor/Core Exit Thermocouple (CETC) Failure.

- IR 4472056; Alarm 2-9-D6 - RVLIS Level Sensor 7B Erratic.

- IR 4482013; 1-9-D6, RVLIS Sensor Uncovered, Sensor 6A (Plenum 27%).

- IR 4488602; Unexpected Alarm on Unit One A-Train RVLIS.

- IR 4508584; Unexpected Alarm 1-9-D6, RVLIS Sensor Uncovered, Sensor 3A.

The Reactor Vessel Level Indication System is described in Appendix E, Requirements Resulting from the Three Mile Island 2 Accident, of the stations Updated Final Safety Analysis Report (UFSAR) as part of a system of instrumentation used to detect inadequate core cooling (ICC) during significant accident scenarios. Operability requirements for RVLIS in operational Modes 1, 2, and 3 are set forth in Section 3.3.3 of the stations Technical Specifications (TS). The Bases for TS 3.3.3 states, in part:

The Reactor Vessel Water Level Monitoring System provides a direct measurement of the liquid level above the fuel. Two channels are required OPERABLE (Train A and Train B). Each channel consists of eight sensors on a probe. For a channel to be considered OPERABLE one of the two sensors in the "head" region and three of the six sensors in the "plenum" region shall be OPERABLE. The level indicated by the OPERABLE sensors represents the amount of liquid mass that is in the reactor vessel above the core. Operability of each sensor may be determined by reviewing the error codes displayed on the control room indicator.

In the cases reviewed, the inspectors noted that the issues typically involved brief or spurious abnormal readings from a single RVLIS sensor, which was insufficient by itself to render the applicable RVLIS channel inoperable. The inspectors also noted, however, that the continuing presence and frequency of these abnormal readings was, at best, becoming a nuisance for control room operators and, at worst, a chronic issue that could eventually challenge RVLIS TS operability.

The inspectors further noted that the licensee was placing an appropriate level of emphasis on this issue; at the conclusion of the inspection period the licensee generated IR 4508208; Potential Trend in Unit 1/Unit 2 RVLIS Issues, within the stations CAP to drive additional engineering reviews into this 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 15, 2022, the inspectors presented the integrated inspection results to Mr. G. Gugle, Site Vice President, and other members of the licensee staff.

On April 1, 2022, the inspectors presented the radiation protection inspection results to Mr. J. Petty, Plant Manager, and other members of the licensee staff.

On May 20, 2022, the inspectors presented the ISFSI Cask Loading inspection results to Mr. G. Gugle, Site Vice President, and other members of the licensee staff.

On June 10, 2022, the inspectors presented the radiation protection inspection results to Mr. G. Gugle, Site Vice President, and other members of the licensee staff.

THIRD PARTY REVIEWS As discussed in IMC 0611, Section 13.01, the inspectors completed a review of the final report issued by the Institute of Nuclear Power Operations (INPO) for the most recent periodic plant performance evaluation of Braidwood Station, which was performed during July 2021 and had a formal exit on September 13, 2021.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60855 ALARA Plans BW-00-22-00325 Dry Cask Storage and Support Activities 0

Calculations BRW-14-0070-N Braidwood Cask Model Update for 2014 ISFSI Campaign 0

BRW-21-0027-N Braidwood Cask Model Update for 2022 ISFSI Campaign 0

Corrective Action 00157367 Entry Into 1BwOA PRI-4 Due to High RCS Activity on 05/05/2003

Documents 1PR06J

244340 Abnormal Noise Emanating from the FHB Crane 04/29/2019

265230 DCS - Indication Found During MPC Delivery Inspection 07/18/2019

270528 MPC 531 Lid Has Minor Indications (Acceptable) 08/08/2019

274522 2019 Braidwood DCS Campaign Lessons Learned 08/26/2019

04323080 DCS PM Partial Performance 03/02/2020

04329064 PCRA to Update BwFP FH-20 FHB Crane Temp 03/24/2020

Requirement

04375525 NOS Finding: M&TE Not Entered for ISFSI Campaign WOs 10/09/2020

04486579 OI Benchmark: Industry Use of Admin Controls for Cask 03/22/2022

Ops

Miscellaneous SFP Boron Sample Results 05/16/2022

2.48-203 Procedure OU-MW-671-300 7B

2.48-204 Holtec RRTI-2788-002 0

2.48-205 EC 628051/Analysis No. BRW-09-0028 and Analysis No. 0, 2, 1A

BRW-09-0029

2.48-206 Holtec Notice HN-01 1

2.48-208 ECR 443383, ISFSI Grillage Polyethylene Bars 0

2.48-212 Holtec FCR 27881002 1

2.48-223 EC 629492/Analysis No. BRW-09-0028 and Analysis No. 0, 2A, 1B

BRW-09-0029

2.48-224 BWNPS 10 CFR 72.212 Evaluation Report 06-01

2.48-226 EC 635339 0

2.48-227 EC 635339 0

2.48-228 EC 635339 0

2.48-229 BWNPS 10 CFR 72.212 Evaluation Report 06-02

2.48-31 Review of PCI/CES and LTS Procedures 0

Inspection Type Designation Description or Title Revision or

Procedure Date

BRW-21-0026-N Braidwood Fuel Selection Package and Alternative List for 0

22 ISFSI Campaign

DIT-BRW-2010- Braidwood Fuel Characterization 12/14/2010

0104

DOC-1023-677 MPC 32 to Braidwood Generating Station 0

NDE Reports 2021-175 MPC Lift Spider Assembly 12/07/2021

Report No. Lid to Shell 05/17/2022

914743-676-01

Report No. Lid to Shell / SN 676 05/17/2022

914743-676-02

Report No. Lid to Shell / SN 676 05/18/2022

914743-676-03

Report No. Lid to Shell / SN 676 05/18/2022

914743-676-04

Procedures BwFP FH-69 HI-TRAC Movement Within the Fuel Building 27

BwFP FH-83 Spent Fuel Cask Contingency Procedures 15

OU-MW-671-300 Forced Helium Dehydration (FHD) for PWRs (ISFSI) 16

PC-CNSTR-OP- Closure Welding of Holtec Multi-Purpose Canisters at Exelon Revision 22

EXE-H-01 Facilities

Self-Assessments NOSA-BRW-20- Independent Spent Fuel Storage Installation Audit Report 10/14/2020

(AR 4370017)

Work Orders 00676183 01 WH-Perform In-Mast Sipping of All Fuel Assemblies 10/18/2004

04673912 01 Fuel BLDG Overhead Crane Lubrication 04/29/2019

05063024 0HC03G INSP of FHB Overhead Crane 06/03/2021

05063029 LR-Yearly Inspection 06/18/2021

05121105 05 ISFSI RX ENG Inventory MPC After Fuel Load 05/17/2022

05123909 MPC Lift Cleat Inspection 12/07/2021

05123918 HI STORM Lift Bracket Inspection 12/07/2021

05123919 Inspect MPC Spider Lift 12/07/2021

05138020 HI-TRAC Trunnion Inspect 02/11/2022

05138021 Lift Yoke Inspection 02/11/2022

71111.01 Miscellaneous Letter from Mr. Greg Gugle to Ms. Marri Marchionda-Palmer, 05/13/2022

Certification of 2022 Summer Readiness

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures 0BwOA ENV-1 Adverse Weather Conditions Unit 0 124

CC-BR-118-1001 Site Implementation of Diverse and Flexible Coping 8

Strategies (FLEX) and Spent Fuel Pool Instrumentation

Program

OP-AA-102-102 General Area Checks and Operator Field Rounds 18

OP-AA-108-107- Station Response to Grid Capacity Conditions 9

1001

OP-AA-108-111- Severe Weather and Natural Disaster Guidelines 24

1001

OP-BR-102-102- Augmented Operator Field Rounds 4

1001

WC-AA-107 Seasonal Readiness 24

71111.04 Corrective Action 4407811 Date Wrong for 1ER-DC05E/Evaluate for Y2K Compliancy 03/10/2021

Documents 4452755 1ER-DC05E Positive Ground Pushed is High Out of Band 10/13/2021

Procedures BwOP AF-E2 Electrical Lineup Unit 2 Operating 11

BwOP AF-M2 Operating Mechanical Lineup, Auxiliary Feedwater, Unit 2 18

BwOP DC-E2 Electrical Lineup Unit 1 Operating-125V DC Division 9

BwOP DG-E1 Electrical Lineup Unit 1 1A Diesel Generator 7

BwOP DG-M1 Operating Mechanical Lineup Unit 1 1A D/G 17

BwOP DG-M2 Operating Mechanical Lineup Unit 1 1B D/G 17

BwOP RH-E2 Electrical Lineup Unit 2 Operating 9

BwOP RH-E2 Electrical Lineup Unit 2 Operating 9

BwOP RH-M4 Operating Mechanical Lineup Unit 2 2B Train 8

71111.11Q Miscellaneous Braidwood Station Licensed Operator Requalification 0

Simulator Scenario Guide, Cycle 22-3 OBE

Procedures OP-AA-101-111- Operations Standards and Expectations 30

1001

OP-AA-101-113 Operator Fundamentals 15

OP-AA-101-113- 4.0 Crew Critique Guidelines 12

1006

OP-AA-103-1-2- Strategies for Successful Transient Mitigation 3

1001

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

Inspection Type Designation Description or Title Revision or

Procedure Date

OP-AA-103-103 Operation of Equipment 2

OP-AA-104-101 Communications 5

OP-AA-108-107- Interface Procedure Between BGE/COMED/PECO and 14

1002 Exelon Generation (Nuclear/Power) for Transmission

Operations

OP-AA-111-101 Operating Narrative Logs and Records 19

OP-AA-300 Reactivity Management 14

TQ-AA-10 Systematic Approach to Training Process Description 7

TQ-AA-150 Operator Training Programs 22

TQ-AA-155 Conduct of Simulator Training and Evaluation 12

TQ-AA-306 Simulator Management 11

TQ-BR-201-0113 Braidwood Training Department Simulator Examination 26

Security Actions

71111.12 Corrective Action 4482320 Boron Accumulation at 1CV8321A 03/03/2022

Documents 4490289 2PL08J Annunciator Panel Has No Power 04/05/2022

4492850 1CV8321A Steam Leak 04/13/2022

4493891 Work Request for 1B EDG Annunciator Power Supply 04/18/2022

4493892 Work Request for 1A EDG Annunciator Power Supply 04/18/2022

Drawings M-64, Sheet 5 Diagram of Chemical and Volume Control and Boron BI

Thermal Regeneration Unit 1

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)

Work Orders 4901183 6 Year Inspection 06/03/2022

71111.13 Corrective Action 4493589 Unexpected Annunciators: 2-21-C8 & 2-21-D8 04/16/2022

Documents 4494966 Scope Expansion of 0SX02D-30" 04/22/2022

4494967 Scope Expansion Inspection of 1SX02B-30" 04/22/2022

4494969 Scope Expansion Inspection of 1SX03A-30" 04/22/2022

4494970 Scope Expansion Inspection of 2SX02B-30" 04/22/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Adverse Condition Monitoring and Contingency Plan 0

(ACMP): SX Leak on Unit 0 CC Heat Exchanger (0SX03A)

Final RICT Record for Unit 1 Station Auxiliary Transformer 05/15/2022

(SAT) 142-1 and 142-2 Work Window

Procedures ER-AA-600 Risk Management 7

ER-AA-600-1023 PARAGON Model Capability 10

ER-AA-600-1042 On-Line Risk Management 13

ER-AA-600-1052 Risk Management Support of RICT 1

ER-AA-600-1053 Calculation of RMAT and RICT for Risk Informed Completion 0

Time Program

ER-BW-600-2001 Braidwood RICT System Guidelines 0

MA-AA-716-004 Conduct of Troubleshooting 19

OP-AA-107 Integrated Risk Management 4

OP-AA-108-117 Protected Equipment Program 7

OP-AA-108-118 Risk Informed Completion Time 2

WC-AA-101-1006 On-Line Risk Management and Assessment 4

Work Orders 4901183 6 Year Inspection 06/03/2022

249849-01 Troubleshoot Annunciator Panel 04/18/2022

253243-01 Ultrasonic Thickness Exam on Line 0SX02D-30" - 0CC01A 05/17/2022

Heat Exchanger Inlet Nozzle

253244-01 Ultrasonic Thickness Exam on Line 1SX02B-30" - 0CC1A 05/04/2022

Heat Exchanger Inlet Nozzle

253245-02 Ultrasonic Thickness Exam on 1SX03A-30" - 1CC01A Heat 05/04/2022

Exchanger Outlet Nozzle

71111.15 Corrective Action 4471553 Reflash of U2 Rod Control Non-Urgent Failure Alarm 01/13/2022

Documents 4492197 1B DG Repair Crack in Manifold 04/11/2022

4494801 SX Piping Leakage at Outlet of U-O CC Hx 04/22/2022

4505042 0B VC Chiller Oil Additions 06/11/2022

Engineering 635793 Install Temporary Power Supply in 2RD03J 1

Changes 636541 Engineering to Evaluate Seal Weld for Cracked 1B DG 0

Manifold

636627 Configuration Control Processing of Design Analysis 0

051853, Revision 005M, for Evaluation of the Structural

Inspection Type Designation Description or Title Revision or

Procedure Date

Integrity of Line 0SX03A-30" per Code Case N-513-4,

Considering the Through Wall Leakage Identified

636646 Operability Evaluation 22-001: Pinhole Leak on a Weld on 0

Line 0SX03A-30"

636646 Operability Evaluation 22-001: Pinhole Leak on a Weld on 0

Line 0SX03A-30"

Miscellaneous BRW-2-2021- ODM: Unit 2 Rod Drive Non-Urgent Failure 0

0304

Procedures CC-AA-309-101 Engineering Technical Evaluations 16

ER-AA-600-1012 Risk Management Documentation 14

OP-AA-106-101- Operational Decision-Making Process 23

1006

OP-AA-108-111 Adverse Condition Monitoring and Contingency Planning 17

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

Work Orders 5214697 IM 2RD03J Fab & Install Temp PS in Parallel with PS1, PS2 05/25/2022

71111.18 Corrective Action 4467108 Unexpected Annunciator 2-10-D6: Rod Control Non-Urgent 12/16/2021

Documents Failure

4468189 Reflash of Unit 2 Rod Control Non-Urgent Failure Alarm 12/24/2021

2-10-D6

4471553 Reflash of Unit 2 Rod Control Non-Urgent Failure Alarm 01/13/2022

Engineering 635793 Install Temporary Power Supply in 2RD03J 1

Changes

Procedures CC-AA-112 Temporary Configuration Changes 29-30

IP-ENG-001 Standard Design Process (EB-17-06) 2

Work Orders 5253243-01 Ultrasonic Thickness Exam on Line 0SX02D-30" - 0CC01A 05/17/2022

Heat Exchanger Inlet Nozzle

71111.19 Procedures ER-AA-335-004 Ultrasonic (UT) Measurement of Material Thickness and 9

Interfering Conditions

71111.22 Corrective Action 4502482 0FX03PA Battery Voltage Low - Failed Acceptance Criteria 05/28/2022

Documents 4502483 0FX03PB Battery Voltage Low - Failed Acceptance Criteria 05/282022

4502484 0FX01PA Battery Voltage Low - Failed Acceptance Criteria 05/28/2022

4502485 0FX01PB and 0FX01PC Battery Voltages Low but Still in 05/28/2022

Band

Inspection Type Designation Description or Title Revision or

Procedure Date

4504183 OOT and Blown Control Power Fuse on 2N-NR8041 06/07/2022

4504563 Cleared Controller Fuse for 2N-NR8042 06/09/2022

4505840 0FX03PA Voltage Low 06/16/2022

4505992 0A Medium Head Flex Pump Won't Stay Running 06/16/2022

4505994 0A High Head Flex Test Connection Bad Fitting 06/16/2022

4506515 0FX03PB Developed Leak from Diesel Oil Filter When 06/20/2022

Started

4507359 0FX03PB Low Head Flex Pump Flow 06/24/2022

4507621 0FX03PB Fuel Oil Leak 06/26/2022

4507623 B High Head Flex Pump Did Not Meet Test Parameters 06/26/2022

4508035 0B High Head Flex Pump High Oil Temp 06/28/2022

Procedures 0BwOS FX-12 FLEX Pump Full Flow Test Surveillance 0

BwISR 3.3.1.6- Quarterly Excore Power Range N44 Axial Flux 44

004 Difference/7300 Delta Flux Penalty Calibration

OP-BR-FX-1003 High Head FLEX Pump Operating Guideline 1

OP-BR-FX-1004 Medium Head FLEX Pump Operating Guideline 0

OP-BR-FX-1005 Low Head FLEX Pump Operating Guideline 1

Work Orders 5011598 0FX01PA (A Train Medium Head FLEX Pump) Performance 06/20/2022

Test

5013180 0FX03PA (A Train Low Head FLEX Pump) Performance 06/16/2022

Test

71114.06 Corrective Action 4504645 Braidwood 2022 Performance Indicator Drill Critique and 06/09/2022

Documents Learnings Operations Support Center

4504679 Braidwood 2022 Performance Indicator Drill Learnings 06/09/2022

Technical Support Center 1 of 2

4504684 Braidwood 2022 Performance Indicator Drill Learnings 06/09/2022

Technical Support Center 2 of 2

4504733 Braidwood 2022 Performance Indicator Drill Learnings 06/09/2022

Main Control Room / Simulator

Procedures EP-AA-1000 Standardized Radiological Emergency Plan 33

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

EP-AA-1001, Braidwood Station On-Shift Staffing Technical Basis 2

Addendum 1

Inspection Type Designation Description or Title Revision or

Procedure Date

EP-AA-1001, Emergency Action Levels for Braidwood Station 7

Addendum 3

71124.03 Corrective Action AR 04435959 0EA01C SCBA Air Compressor PM's Needed Air 07/21/2021

Documents Replacement

AR 04490491 SCBA Compressor Out of Service 04/05/2022

Miscellaneous Trace Analytics SCBA Grade D Quality Air Report 05/05/2022

Air One Equipment SCBA Hydrostatic Testing Results 01/25/2022

Procedures RP-AA-444 Controlled Negative Pressure (CNP) Fit Testing 12

RP-AA-700-1246 Operation of Air Samplers 6

RP-AA-825 Maintenance, Care, and Inspection of Respiratory Protective 9

Equipment

71124.04 Calibration Calibration of the Accuscan II WBC System at the Exelon 02/23/2022

Records Generating Station

Miscellaneous Dose Assessment for a Declared Pregnant Worker. 02/01/2022

Dose Assessment for a Declared Pregnant Worker. 02/20/2021

Braidwood Dry Activated Waste Part 61 Analysis 2020

Procedures RP-AA-12 Internal Dose Control Program Description 2

RP-AA-441 TEDE ALARA Evaluation 12

RP-AA-700-1235 Operation and Calibration of the PM-12 Gamma Portal 5

Monitor

71124.05 Calibration Serial Number Mirion Telepole II 07/27/2021

Records 0019520

Serial Number Argos 5 Monitor 03/17/2022

1011-279

Serial Number Thermo Scientific PM12 03/22/2022

2060

Serial Number Thermo Scientific PM12 12/03/2021

2082

Serial Number Thermo Scientific PM12 Unit 1 Containment Access Facility 03/23/2022

2084

Serial Number Thermo Scientific SAM12 03/17/2022

235A

Serial Number Ludlum Model 30 02/25/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

26144

Serial Number Mirion RDS-31 09/21/2021

2B.106

Serial Number Ludlum Model 12-4 02/25/2021

336338

Serial Number Bicron RSO-50E 03/14/2022

C613F

Corrective Action AR 04431313 Low Flow and Pump (2PR30PB) Turning Off on 2PR3DJ 07/24/2021

Documents AR 04444789 Unexpected Alarm: 0AR68J High Alarm 09/05/2021

AR 04486858 U1 CAF PM12 12010 Needs Battery Replaced 03/23/2022

Work Orders 04956514 1PR28J Calibration of Effluent Gaseous Rad Monitor Plant 01/27/2021

Ventilation Monitor

04999329-01 Calibration Liquid Effluent Radiation Monitor Station 09/01/2021

Blowdown Line

71151 Miscellaneous NRC Performance Indicator Data; Mitigating Systems 04/01/2021 -

Safety System Functional Failures 03/31/2022

NRC Performance Indicator Data; Mitigating Systems 04/01/2021 -

Mitigating System Performance Index for Emergency AC 03/31/2022

Power

NRC Performance Indicator Data; Mitigating Systems 04/01/2021 -

Mitigating Systems Performance Index for High Pressure 03/31/2022

Injection

Procedures LS-AA-2001 Collecting and Reporting of NRC Performance Indicator 17

Data

LS-AA-2080 Monthly Data Elements for NRC Safety System Functional 8

Failures

LS-AA-2200 Mitigating System Performance Index Data Acquisition and 7

Reporting

71152A Corrective Action 4474052 Level 3 Configuration Control: Incorrect Connection of Test 01/26/2022

Documents Equipment

4475596 4.0 Critique - Volume Control Tank Pressure Abnormal 02/02/2022

Indication

4475837 Maintenance Department For-Cause Management Review 02/03/2022

Meeting Results

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures BwAR 2-9-B2 Volume Control Tak (VCT) Pressure High/Low 54

BwIP 2P-0120 Calibration of Charging Header Pressure Loop 2P-0120 (CV) 1

BwOP RP-11A18 2PA06J Panel Appendix 6

NO-AA-10 Quality Assurance Topical Report (QATR) 98

PI-AA-120 Issue Identification and Screening Process 12

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

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

PI-AA-125-1004 Effectiveness Review Manual 2

Work Orders 5063738 2P-0120 Charging Header Pressure Loop 01/26/2022

71152S Corrective Action 4442055 1-9-D6 - Unexpected Main Control Room Alarm -RVLIS 08/23/2021

Documents Sensor Uncovered

4442887 1-9-D6 - Unexpected Main Control Room Alarm - RVLIS 08/26/2021

Sensor Uncovered

4450389 Unexpected Main Control Room Alarm - Reactor Vessel 10/03/2021

Level Indication System (RVLIS) Sensor/Core Exit

Thermocouple (CETC) Failure

4472056 Alarm 2-9-D6 - RVLIS Level Sensor 7B Erratic 01/15/2022

4482013 1-9-D6, RVLIS Sensor Uncovered Sensor 6A (Plenum 27%) 03/02/2022

4488602 Unexpected Alarm on Unit One-A RVLIS 03/30/2022

4508208 Potential Trend in Unit 1/Unit 2 RVLIS Issues 06/29/2022

4508584 Unexpected Alarm 1-9-D6, RVLIS Sensor Uncovered 06/30/2022

Sensor 3A

2