ML25344A058
| ML25344A058 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/10/2025 |
| From: | Dariusz Szwarc NRC/RGN-III/DORS/RPB3 |
| To: | Mudrick C Constellation Energy Generation, Constellation Nuclear |
| References | |
| EAF-RIII-2025-0159 IR 2025003 | |
| Download: ML25344A058 (0) | |
Text
EAF-RIII20250159 Christopher H. Mudrick Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Office (CNO)
Constellation Nuclear 200 Energy Way, KSA-3N Kennett Square, PA 19348
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2025003 AND 05000457/2025003 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Christopher H. Mudrick:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station. On November 24, 2025, the NRC inspectors discussed the results of this inspection with A. Schuerman, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300.
On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the regional offices an extension on the issuance of the calendar year 2025, third quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, fourth quarter integrated inspection reports, which will be issued 45 days after the fourth quarter ends on December 31, 2025.
December 10, 2025
C. Mudrick 2
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, Dariusz Szwarc, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Szwarc, Dariusz on 12/10/25
C. Mudrick 3
Letter to Christopher H. Mudrick from Dariusz Szwarc dated December 10, 2025.
SUBJECT:
BRAIDWOOD STATION - INTEGRATED INSPECTION REPORT 05000456/2025003 AND 05000457/2025003 AND EXERCISE OF ENFORCEMENT DISCRETION DISTRIBUTION:
Rodney Clagg RidsNrrDorlLpl3 RidsNrrPMBraidwood Resource RidsNrrDroIrib Resource Jack Giessner Mohammed Shuaibi Diana Betancourt-Roldan John Pelchat Jared Heck Jennifer Dalzell R3-DORS ADAMS Accession Number: ML25344A058
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RIII NAME DSzwarc:anm DATE 12/10/2025 OFFICIAL RECORD COPY
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000456 and 05000457 License Numbers:
NPF-72 and NPF-77 Report Numbers:
05000456/2025003 and 05000457/2025003 Enterprise Identifier:
I20250030048 Licensee:
Constellation Nuclear Facility:
Braidwood Station Location:
Braceville, IL Inspection Dates:
July 01, 2025, to September 30, 2025 Inspectors:
R. Bowen, Illinois Emergency Management Agency J. Cassidy, Senior Health Physicist T. Hooker, Health Physicist J. McPherson, Reactor Operations Engineer G. Roach, Senior Operations Engineer J. Robb, Operations Engineer J. Robbins, Senior Resident Inspector P. Smagacz, Resident Inspector Approved By:
Dariusz Szwarc, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety
2
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 Type Issue Number Title Report Section Status EDG EAF-RIII20250159 Failure to Comply with 10 CFR Part 37 71124.08 Closed
3 PLANT STATUS Unit 1 began the inspection period at rated thermal power. On July 30, 2025, Unit 1 tripped due to a lightning strike (EN 57839/LER 202500101). All systems responded as designed. The unit was restarted on July 31, 2025, and achieved full power on August 2, 2025. The unit remained at or near rated thermal power until September 16, 2025, when the unit began coasting down for planned refueling outage A1R25. The unit was at approximately 90 percent rated thermal power at the end of the inspection period.
Unit 2 began the inspection period at rated thermal power. On July 10, 2025, the unit reduced rated thermal power to 89 percent to repair a condenser tube leak. The unit returned to full power on July 14, 2025. The unit remained at or near rated thermal 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 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.
REACTOR SAFETY 71111.04 - Equipment Alignment Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the Unit 1 emergency diesel generators (EDGs) during the weeks ending September 6 through October 4, 2025.
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Fire Zone FZ 11.3A1, auxiliary building, 364' elevation, safety injection pump 1A room during the week ending August 16, 2025 (2)
Fire Zone FZ 11.2D1, auxiliary building, 346' elevation, residual heat removal pump 1B room during the week ending August 16, 2025
4 (3)
Fire Zone FZ 11.4A2, auxiliary building, 383' elevation, Unit 2 auxiliary feedwater pump diesel room during the week ending August 16, 2025 71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03) (1 Sample)
(1)
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between the weeks of August 19, 2025, and September 23, 2025, and the biennial written examinations completed in September 2024.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
(1)
Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on September 13, 2024.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test administered during the week of August 25, 2025.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
5 Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(2 Samples)
The inspectors observed and evaluated the following activities performed by licensed operators in the facility's main control room:
(1) various activities involving on-watch operations crews in the main control room during a downpower for a Unit 2 condenser tube leak during the week ending July 12, 2025 (2) various activities involving on-watch operations crews in the main control room during a restart of Unit 1 during the week ending August 2, 2025 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated the following licensed operator training activity, which included the administration of the annual requalification operating test required by 10 CFR 55.59(a)(2) in the facility's control room simulator:
(1) a complex casualty graded scenario involving a crew of licensed operators was observed in facilitys simulator during the conduct of the annual requalification operating test during the week ending September 6, 2025 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)
EDG emergency air supply bottles during the week ending August 30, 2025 (2) auxiliary feedwater air operated injection valves during the weeks ending September 6 through 20, 2025 Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1) main steam isolation valve (MSIV) air accumulator regulators during the weeks ending September 6 through 13, 2025
6 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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) review and evaluation of the risk associated with risk informed completion time (RICT) associated with instrument 1P0545 repairs and over temperature delta temperature (OTDT) needs calibration, as documented in OP-AA108118, Attachment 2, RICT record during the week ending August 9, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
(1) evaluation of the operability of the 1A diesel generator due to a fuel oil leak, as documented in Action Request (AR) 4878462 during the week ending July 12, 2025 (2) evaluation of the operability of the 1A diesel generator due to a lube oil leak, as documented in AR 4878458 during the week ending July 19, 2025 (3) evaluation of the operability of the 2A diesel generator due to a sheared piece of tubing, as documented in AR 4885105 during the week ending August 2, 2025 (4) evaluation of the operability of the 1A EDG due to a potential issue with EDG ventilation, as documented in AR 4895775 during the week ending September 13, 2025 (5) evaluation of the operability of 2P0457 pressurizer pressure loop, as document in AR 4891362 during the week ending September 13, 2025 (6) evaluation of the operability of the 2B EDG after a failed fast start, as documented in AR 4900643 during the week ending September 27, 2025 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 or permanent modifications:
(1) permanent plant modification per Engineering Change (EC) 643635, Appendix J Local Leak Rate Scope Reduction - Penetrations P1, P16, and P41, Revision 0 during the week ending July 17, 2025
7 71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
(1) functional and operational testing of the 1D steam generator pressure indicator following replacement, as documented in Work Order (WO) 5701998 during the week ending August 16, 2025 (2) functional and operational testing of Unit 1, power range instrument N43 following 15-year replacement of power supplies, as documented in WO 1835382 during week ending August 30, 2025 (3) functional and operational testing of 2CC9412A following maintenance, as documented in WO 4921862 during week ending August 30, 2025 (4) functional and operational testing of 1PDS-VD044 DG vent system fan and 1VD01CA differential pressure switch following maintenance, as documented in WO 5720055 during week ending September 20, 2025 (5) functional and operational testing of 1FC8765 after maintenance, as documented in WO 5430031 during the week ending August 30, 2025 Surveillance Testing (IP Section 03.01) (2 Samples)
(1) 1BwOSR 3.8.1.21; Unit One 1A Diesel Generator Operability Surveillance, as documented in WO 5683714 during the week ending July 5, 2025 (2) 1BwOSR 5.5.8.CC6A; Group A IST Requirements for Component Cooling Pump (1CC01PA), as documented in WO 5660549 during the week ending July 12, 2025 RADIATION SAFETY 71124.07 - Radiological Environmental Monitoring Program Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements.
8 71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation Radioactive Material Storage (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
(1) snubbers stored in top loading sealand container Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1) radioactive waste building resin processing equipment Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)
Dry Active Waste (DAW)
(2) 0WX0ST resin Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1) radioactive waste shipment number RWS24014; resin liner in cask RT100 (2) radioactive waste shipment number RWS24019; DAW & metals in shielded seavan (3) radioactive waste shipment number RWS25001; resin liner PO71139886 in cask 14215H21 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
(1)
Unit 1 (July 1, 2024, through June 30, 2025)
(2)
Unit 2 (July 1, 2024, through June 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
(1)
Unit 1 (July 1, 2024, through June 30, 2025)
(2)
Unit 2 (July 1, 2024, through June 30, 2025)
9 MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
(1)
Unit 1 (July 1, 2024, through June 30, 2025)
(2)
Unit 2 (July 1, 2024, through June 30, 2025)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
(1)
Unit 1 (October 1, 2024, through June 30, 2025)
(2)
Unit 2 (October 1, 2024, through June 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
Unit 1 (October 1, 2024, through June 30, 2025)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)
Unit 1 (October 1, 2024, through June 30, 2025) 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
Review and assessment of the stations corrective actions for an out of tolerance condition identified during testing as discussed in AR 4891362 during the week ending September 20, 2025.
71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03) (1 Sample)
(1)
Review and assessment of licensee and plant response to the Unit 1 automatic reactor trip on July 30, 2025, due to an OTDT reactor protection system actuation as documented in NRC Event Notification57893, during the week ending August 2, 2025. No performance deficiency nor violation of NRC requirements was identified.
10 INSPECTION RESULTS Enforcement Discretion Enforcement Action EAF-RIII20250159: Failure to Comply with 10 CFR Part 37 71124.08
==
Description:==
On January 15, 2016, the licensee was issued NRC Inspection Report Nos.
05000456/2016407 and 05000457/2016407, which documented a licensee identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program.
The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14001, Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52.
Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for enforcement discretion established within the Interim Enforcement Policy (IEP) discussed within NRCs Enforcement Policy, Section 9.3.
Corrective Actions: As specified in the NRCs Enforcement Policy, Section 9.3, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action.
Enforcement:
Violation: On January 15, 2016, the licensee was issued NRC Inspection Report Nos.
05000456/2016407 and 05000457/2016407. The inspectors determined that the previously identified violation remains.
Basis for Discretion: This violation met all of the criteria for Enforcement Discretion as described in NRCs Enforcement Policy, Section 9.3, Enforcement Discretion for Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material (10 CFR Part 37).
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On November 24, 2025, the inspectors presented the integrated inspection results to A. Schuerman, Site Vice President, and other members of the licensee staff.
On July 25, 2025, the inspectors presented the radiation protection inspection results to S. MacArtney, Maintenance Director, and other members of the licensee staff.
On August 29, 2025, the inspectors presented the 2025 licensed operators requalification program inspection results to A. Schuerman, Site Vice President, and other members of the licensee staff.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 4899212 1DG5168B Valve Handle Comes Off 09/19/2025 4899221 1HS-DG223 Needs EPN 09/19/2025 4899235 1B DG Left Air Manifold High 09/19/2025 Corrective Action Documents 4900339 1B EDG DO Supply Pipe Clamp Dampening Material Degraded 09/24/2025 Corrective Action Documents Resulting from Inspection 4899608 DG Valve Tag Description Typos 09/22/2025 BwOP DG-E1 Electrical Lineup - Unit 1 1A Diesel Generator 7
BwOP DG-E2 Electrical Lineup - Unit 1 1B Diesel Generator 6
BwOP DG-M1 Operating Mechanical Lineup Unit 1 1A D/G 17 71111.04 Procedures BwOP DG-M2 Operating Mechanical Lineup Unit 1 1B D/G 17 Pre-Fire Plan
Pre-Fire Plan
- 118 FZ 11.3A-1, AB 364' Safety Injection Pump 1A Room 3
71111.05 Fire Plans Pre-Fire Plan
71111.11A Miscellaneous TQ-AA-150F25 LORT Annual Exam Status Report Rev. 007 Calculations 1BwGP 1007T4 Calculation of Estimated Critical Condition from Nuclear Fuel, Westinghouse, or Beacon Supplied Values 15 Root Cause Evaluation for IR#4772085 05/24/2024 AR 04893981 LORT Annual Exam Security Procedure Non-Compliance 08/28/2025 Corrective Action Documents PA-240124-001 Performance Analysis for Shear Pin Replacement 01/24/2024 Braidwood 24-month Requalification Program (2023-2025)
Training Cycle 23-6 Licensed Operator Attendance Records Training Cycle 24-4 Licensed Operator Attendance Records BwVS 500-6 Low Power Physics Test Program 48 OP-AA-105-102 Reactivation of License Log 17 71111.11B Miscellaneous OP-AA-105-102 Reactivation of License Log (Completed for two operators)
12 Inspection Procedure Type Designation Description or Title Revision or Date SRB 24-1 Simulator Review Board 03/05/2024 SRB 24-2 Simulator Review Board 11/05/2024 TQ-AA-150-F25 LORT Annual Examination Status Report 09/27/2024 TQ-AA-155-F04 Simulator Evaluation Form - Individual (Completed) 08 TQ-AA-155-F05 Simulator Evaluation Form - CREW (Completed) 15 TQ-AA-306 ATT 10 PWR Moderator Temperature Coefficient of Reactivity Post-Outage 06/20/2024 TQ-AA-306 ATT 10 PWR Moderator Temperature Coefficient of Reactivity Pre-Outage 11/04/2023 TQ-AA-306 ATT 11 PWR Rod Worth Coefficient of Reactivity Pre-Outage 11/04/2023 TQ-AA-306 ATT 11 PWR Rod Worth Coefficient of Reactivity Post-Outage 06/20/2024 TQ-AA-306 ATT 12 PWR Boron Coefficient of Reactivity Pre-Outage 11/04/2023 TQ-AA-306 ATT 13 PWR Xenon Worths Pre-Outage 11/04/2023 TQ-AA-306 ATT 16 PWR Approach to Criticality Using Boric Acid Pre-Outage 11/04/2023 TQ-AA-306 ATT 17 PWR Approach to Criticality Using Control Rods Pre-Outage 11/04/2023 TQ-AA-306 ATT 17 PWR Approach to Criticality Using Control Rods Post-Outage 06/20/2024 TQ-AA-306-F-03 POST EVENT SIMULATOR TEST: Steam Generator Lo-2 Reactor Trip 07/02/2024 TQ-AA-306-F-03 Post Event Simulator Test: Grid Transient AR 04799109 10/09/2024 TQ-AA-306-F-03 POST EVENT SIMULATOR TEST: 16B Heater Normal Level Control Valve 1HD011B Sticking 06/03/2025 TQ-AA-306-F-03 Braidwood Real Time Test, Rt-1 Cycle 25 Core Load Testing 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 1 - Manual Reactor Trip 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 2 - Simultaneous Trip of All Main Feedwater Pumps 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 3 - Simultaneous Closure of All 07/17/2025
13 Inspection Procedure Type Designation Description or Title Revision or Date Main Steam Isolation Valves TQ-AA-306-F-03 Braidwood Transient Test 4 - Simultaneous Trip of All Reactor Coolant Pumps 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 5 - Trip of Any Single Reactor Coolant Pump 07/17/2025 TQ-AA-306-F-03 BRAIDWOOD TRANSIENT TEST 6 - TURBINE TRIP < P-8 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 7 - Maximum Rate Ramp 100%
To 75% To 100%
07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 8 - Lbloca with Loop 07/16/2025 TQ-AA-306-F-03 Braidwood Transient Test 9 - Maximum Size Main Steam Line Rupture 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 10 - Slow Primary Depress Due to Open Porv Without Charging Pumps 07/17/2025 TQ-AA-306-F-03 Braidwood Transient Test 11 - Maximum Design Load Rejection 07/17/2025 TQ-AA-306-F-20 Simulator Scenario Based Testing Checklist (LORT Scenario Number 2531) 04/30/2025 TQ-AA-306-F-20 Simulator Scenario Based Testing Checklist (LORT Scenario Number 2541) 06/26/2025 TQ-AA-306-F-20 Simulator Scenario Based Testing Checklist (ILT NRC 2023 Exam Scenario 1) 10/16/2023 TQ-AA-306-F-20 Simulator Scenario Based Testing Checklist (NRC 2023 Exam Scenario 2) 10/16/2023 TQ-AA-306-F-20 Simulator Scenario Based Testing Checklist (NRC 2023 Exam Scenario 3) 10/17/2023 TQ-BR-302-0103 Braidwood Simulator Steady State Testing Ss-1 (100%)
06/17/2025 TQ-BR-302-0103 Braidwood Simulator Steady State Testing Ss-1 (75%)
06/24/2025 TQ-BR-302-0103 Braidwood Simulator Steady State Testing Ss-1 (54%)
06/24/2025 NF-AP-181 Byron and Braidwood Rod Worth Testing Scope Decision Review Form NF-AP-181 PWROG-19014-P HZP BOL MTC Testing Scope Decision Review Form for Byron and Braidwood TQ-AA-150 Operator Training Programs 26 Procedures TQ-AA-306 Simulator Management 13
14 Inspection Procedure Type Designation Description or Title Revision or Date TQ-BR-150-F31 (LORT)
Training Program
Description:
Licensed Operator Requalification Training Program (LORT) 02 TQ-BR-201-0113 Braidwood Training Department Simulator Examination Security Actions 30 Self-Assessments AR 04845283 Pre-71111.11 & Annual Simulator Compliance 05/14/2025 05303923 Perform Low Power Physics Test Program 05/05/2024 SWR 0138723 Nuclear Instrument cabinet power supply failure 11/08/2023 SWR 0138802 Add PPC points for PZR PORV/Safety Tailpipe Temps and Rate of Change 12/19/2023 SWR 0138900 Adjust Refueling Water Storage Tank Low Setpoint 02/15/2024 SWR 0139079 1 Hour Lost Time Due to ECCS Reset Buttons Not Functioning 05/14/2024 SWR 0139092 OA WS Pump Stator Temperature Reaches Alarm Setpoint 05/20/2024 SWR 0139240 Must reset MST With Each IC Reset To Prevent Partial Simulator Failure 08/07/2024 SWR 0139300 Exam Related 09/06/2024 SWR 0139341 STC Simulator Firewall Ruleset Consolidation 10/03/2024 SWR 0139486 H2 Temperature Meter Sticking 01/30/2025 SWR 0139596 SG 1A/1B WR SGWL Yokogawa Fails Intermittently 03/24/2025 Work Orders SWR 0139786 Add PPC Alarm for Feedwater Regulating Valves 06/25/2025 HU-AA-104-101 Procedure Use and Adherence 9
OP-AA-101-111-1001 Operations Standards and Expectations 36 OP-AA-101-113 Operator Fundamentals 20 71111.11Q Procedures OP-AA-101-113-1006 4.0 Crew Critique Guidelines 14 4815722 2A MSIV Air Pump Regulator Seems to be Degraded 11/06/2024 4827290 MSIV Air Regulator Trend 01/03/2025 4837397 1AF005F in Mid Position Following Stroke from RSDP 02/14/2025 4866722 TRM 3.7.g to Go Past 30 Days for 1AF005F 05/18/2025 4867669 1AF005E Did Not Go Full Open 05/21/2025 4869010 2AF005D Exceeds Stroke Closed Alert Time Limit 05/25/2025 71111.12 Corrective Action Documents 4876951 2D MSIV Air Pump Regulator Degraded 06/27/2025
15 Inspection Procedure Type Designation Description or Title Revision or Date 4888258 2D MSIV Air Pump Regulator Degraded 08/04/2025 4892892 2D MSIV Air Pump Regulator Degraded 08/24/2025 Drawings D-10239 Schematic for A/DV Self Contained Hydraulic Acutator K
0BwOS OALE-Q1 Operating Abnormal Procedures Local Equipment Check Surveillance 44 1BwOSR 3.6.3.5.AF-1B Unit One Train B Auxiliary Feedwater Valve Stroke Surveillance 21 ER-AA-2030 Conduct of Equipment Reliability Manual 31 Procedures SM-AA-3019 Parts Quality Initiative (PQI) 15 Work Orders 5658148 Operating Abnormal Procedures Local Equipment Check Quarterly Surveillance 07/22/2025 Corrective Action Documents 4888466 1TY-0421G & 1TY-0421A3 Cards Found Defective 1T-0421 Loop 08/05/2025 None PARAGON RMTS Report for 1P-0545 08/01/2025 OP-AA-108-118, Initial RICT Record for 1PT-0545 and 1B OTDT requires Calibration 08/01/2025 Miscellaneous OP-AA-108-118, Final RICT Record for 1P-0545 and 1B OTDT Requires Calibration 08/05/2025 71111.13 Procedures OP-AA-108-118 Risk Informed Completion Time 3
4878458 1A DG Lower Lube Oil Cooler Oil Leak 07/02/2025 4878462 Fuel Oil Leak from 1PY-DG8035A Diaphragm 07/02/2025 4885105 2A DG Starting Air Compressor #1 Running Continuously /
Air Leak 07/24/2025 4891362 2PB-0457B 0-10 V Signal Found OOT During WO 5439299 08/19/2025 4895775 Unexpected Annunciator 1VD01JA-1-A6 09/06/2025 Corrective Action Documents 4900643 2B EDG Failed Fast Start 09/25/2025 20E-1-4030VD01 Diesel Generator Room 1A HVAC System Ventilation Fan 1A 1VD01CA M
20E-1-4030VD03 Diesel Generator Room 1A HVAC System Ventilation &
Exhaust Fans Auxiliary Relays, Switches & Alarms - Part 1 P
Drawings 20E-1-4030VD15 Diesel Generator Room HVAC System Ventilation Annunciator Panel 1VD01JA G
71111.15 Engineering Evaluations EC 405348 DG Closed System Leak Guidance (Lube Oil, Jacket Water, and Fuel Oil) 0
16 Inspection Procedure Type Designation Description or Title Revision or Date 406445 Appendix J Scope Reduction for Type C Local Leak Rate Testing Penetration P-28 0
Engineering Changes 643635 Appendix J Local Leak Rate Scope Reduction -
Penetrations P-1, P-16, and P-41 0
71111.18 Miscellaneous NEI 94-01 Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J 3-A 1012028 Verify Sealtight Conduit Connectors Tight for 2CC9412A 01/04/2010 1019847 Replace Fuse for Extent of Condition - 2AP21E-K3 01/22/2010 1397634 MCC Bucket as found wiring does not match EC Prints 08/06/2012 1502004 Replace 2CC9412A R/C Contactor - 2AP21E-K3 04/15/2013 4546249 WO 5137542-01 1CC01PA Coupling Issue Expanded Scope 01/03/2023 4546832 1CC01PA Work Delays 01/05/2023 4546923 1CC01PA Work Delays 01/06/2023 4546989 1CC01PA coupling gap issue 01/06/2023 4549595 4.0 Critique 1CC01PA 01/20/2023 4690196 1CC9412B Leak-by Prevented Relief Valve Replacement 07/12/2023 4759610 1CC9507B Leak-by Identified During Troubleshooting 03/20/2024 4762995 Roll-up of Troubleshooting to Isolate 1CC9422B 04/02/2024 4824693 Fuel Transition Impact: 18 Month PR NIs Surveillance Timing 12/18/2024 4869447 Unexpected Alarm 1-10-B4, PWR Rng Lower Det Flux Dev High 05/30/2025 4875425 Unexpected Alarm 1-10-C4 06/23/2025 4878458 1A DG Lower Lube Oil Cooler Oil Leak 07/02/2025 4878465 Damaged Cable Insulation for 1PT-DG704A 07/02/2025 4878468 Unidentified Fuel Oil Leak 1A DG Top, West Side 07/02/2025 4878558 NI Related Ovation Alarms 07/03/2025 Corrective Action Documents 4884475 Unexpected alarm 1-10-C4, PWR RNG Channel Dev 07/23/2025 Drawings 1F-FC-01 Fuel Pool Cooling System E
1BwOSR 0.1-1,2,3 Unit One Modes 1, 2, and 3 Shiftly and Daily Operating Surveillance 104 71111.24 Procedures ER-AA-335-004 Ultrasonic (UT) Measurement of Material Thickness and Interfering Conditions 10
17 Inspection Procedure Type Designation Description or Title Revision or Date 1835382 1N-NR4083 Replace All Power Supplies 08/14/2025 4921862 2AP21E-K3 Starter Diagnostic Test and Control Power Fuse Replacement 08/07/2025 5430031 1FC8765 Found to Have Internal Leak-by 08/27/2025 5660549 IST - For 1CC9463A/B 0CC9464 - ASME SRV RQMTS for 1CC01PA 07/08/2025 5683714 LRIST-1A D/G Operability Monthly 07/02/2025 5701998 1D SG Steam Pressure Indicator Failed High 08/04/2025 Work Orders 5720055 Unexpected Annunciator 1VD01JA-1-A6 09/11/2025 04417340 1st Quarter 2021 Radiochemistry Crosscheck 04/18/2021 04483926 2021 Control Dose OSLDs 03/10/2022 04532907 Power Supply Issue at BD-03 10/28/2022 04666583 NOS ID: Provide Explanation in the ODCM 03/31/2023 04733327 2nd QTR OSLDs 01/19/2024 04734642 5-Year OSLD Baseline Anomalies 01/22/2024 04852827 Change to ODCM Process and Procedure 04/03/2025 Corrective Action Documents 04880690 ODCM Remp Provider 07/11/2025 Braidwood Sampling Anomalies various Annual Radiological Environmental Operating Report various Annual Radiological Groundwater Protection Program Report various Land Use Census various Miscellaneous Well Sample Analyses various CY-AA-170-000 Radioactive Effluent and Environmental Monitoring Programs 7
CY-AA-170-100 Radiological Environmental Monitoring Program 2
CY-AA-170-1000 Radiological Environmental Monitoring Program and Meteorological Program Implementation 13 CY-AA-170-1001 Environmental Dosimetry - Performance Specifications, Testing, and Data Analysis 1
CY-AA-170-1100 Quality Assurance for Radiological Monitoring Programs 4
CY-BR-170-301 Offsite Dose Calculation Manual 11 71124.07 Procedures EN-AA-408 Radiological Groundwater Protection Program 3
18 Inspection Procedure Type Designation Description or Title Revision or Date EN-AA-408-4000 Radiological Groundwater Protection Program Implementation 14 Self-Assessments NOSA-BRW 03 Chemistry, Radwaste, Effluent and Environmental Monitoring Audit Report 04/05/2023 Corrective Action Documents Resulting from Inspection AR 04884453 NRC ID: No locks on Radioactive Materials Trailers 07/22/2025 22 DAW 22 DAW Ave 06/01/2022 23 DAW 23 DAW Ave 04/05/2024 24 DAW 24 DAW Ave 03/11/2025 24 DAW Waste Stream Review and Scaling Factor Determination 03/11/2025 Memo #2018-02 Radiological Controls for Condensate Polisher Resin B-25 Boxes 08/02/2021 Miscellaneous SRRS ID 2B.127 RP-AA-800 2025 Semi-annual Source Inventory and Leak Test 01/16/2025 RP-AA-500-1001 Control of RAM Storage Areas and Containers Stored Outside 15 RP-AA-600 Radioactive Material/Waste Shipments 19 RP-AA-602-1002 Loading Dry Active Waste and Other Waste Forms for Energy Solutions Waste Acceptance Guide (WAG-501) 2 RP-AA-605 10 CFR 61 Program 15 RW-AA-100 Process Control Program for Radioactive Wastes 12 Procedures RW-AA-100 Process Control Program for Radioactive Wastes 12 AR 04710974 Part 37 Implementation and Part 37 Security Plan Compliance 01/15/2024 AR 04716439 02 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 11/08/2024 Self-Assessments AR 04755696 Part 37 Implementation and Part 37 Security Plan Compliance 02/10/2025 71124.08 Shipping Records Radioactive Waste Shipment Number RWS24-014 Resin Liner in Cask RT-100 02/23/2024
19 Inspection Procedure Type Designation Description or Title Revision or Date Radioactive Waste Shipment Number RWS24-019 DAW & Metals in Shielded Seavan 10/25/2024 Performance Indicator Data for MS09: Residual Heat Removal Systems for Units 1 and 2 07/01/2024 -
06/30/2025 Performance Indicator Data for MS10: Cooling Water Systems for Units 1 and 2 07/01/2024 -
06/30/2025 Performance Indicator Data for MS08: Heat Removal Systems for Units 1 and 2 07/01/2024 -
06/30/2025 LS-AA-2090 Monthly Data Elements for NRC ROP Indicator -
Reactor Coolant System (RCS) Specific Activity various LS-AA-2140 Monthly Data Elements for NRC ROP Indicator -
Occupational Exposure Control Effectiveness various 71151 Miscellaneous LS-AA-2150 Monthly Data Elements for NRC ROP Indicator -
RETS/ODCM Radiological Effluent Occurences various 4101654 Trend 7300 NAL Cards 02/07/2018 4366128 WO 4890866 2PB-0457B OOT 0-10 V signal 08/28/2020 4509290 2PB-0457A/B 0-10 V Signal OOT during WO 5084086 07/05/2022 Corrective Action Documents 4891362 2PB-0457B 0-10 V Signal found OOT during WO 5439299 08/19/2025 Drawings 20E-2-4031RY03 LOOP Schematic Diagram Pressurizer Pressure Protection III (2PT0457) Protection Cabinet 3 (2PA03J)
K Miscellaneous Westinghouse IB-NLP 7300 7300 Isolator and Loop Power Supply Instruction Bulletin 0
71152A Procedures BwISR 3.3.1.10-M239 Operational Test and Channel Verification / Calibration for LOOP P-0457, Pressurizer Pressure Protection Channel III Cabinet 3 32