IR 05000456/2025003
| 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
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 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
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
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
- (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.
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
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
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,
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.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
& Transportation
Radioactive Material Storage (IP Section 03.01)
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)===
- (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)
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)
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) 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.
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.
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
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
BwOP DG-E2
Electrical Lineup - Unit 1 1B Diesel Generator
BwOP DG-M1
Operating Mechanical Lineup Unit 1 1A D/G
Procedures
BwOP DG-M2
Operating Mechanical Lineup Unit 1 1B D/G
Pre-Fire Plan
- 109
FZ 11,2D-a, AB 346' RHR Pump 1B Room
Pre-Fire Plan
- 118
FZ 11.3A-1, AB 364' Safety Injection Pump 1A Room
Fire Plans
Pre-Fire Plan
- 138
FZ 11.4A-2, AB 383' Unit 2 Aux. Feedwater Pump Diesel
Room
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
Root Cause Evaluation for IR#4772085
05/24/2024
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
Reactivation of License Log
Miscellaneous
Reactivation of License Log (Completed for two operators)
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)
TQ-AA-155-F05
Simulator Evaluation Form - CREW (Completed)
TQ-AA-306 ATT
PWR Moderator Temperature Coefficient of Reactivity
Post-Outage
06/20/2024
TQ-AA-306 ATT
PWR Moderator Temperature Coefficient of Reactivity
Pre-Outage
11/04/2023
TQ-AA-306 ATT
PWR Rod Worth Coefficient of Reactivity Pre-Outage
11/04/2023
TQ-AA-306 ATT
PWR Rod Worth Coefficient of Reactivity Post-Outage
06/20/2024
TQ-AA-306 ATT
PWR Boron Coefficient of Reactivity Pre-Outage
11/04/2023
TQ-AA-306 ATT
11/04/2023
TQ-AA-306 ATT
PWR Approach to Criticality Using Boric Acid Pre-Outage
11/04/2023
TQ-AA-306 ATT
PWR Approach to Criticality Using Control Rods Pre-Outage
11/04/2023
TQ-AA-306 ATT
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
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
Byron and Braidwood Rod Worth Testing Scope Decision
Review Form
PWROG-19014-P HZP BOL MTC Testing Scope Decision
Review Form for Byron and Braidwood
Operator Training Programs
Procedures
Simulator Management
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
TQ-BR-150-F31
(LORT)
Training Program Description: Licensed Operator
Requalification Training Program (LORT)
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
Self-Assessments AR 04845283
Pre-71111.11 & Annual Simulator Compliance
05/14/2025
05303923
Perform Low Power Physics Test Program
05/05/2024
Nuclear Instrument cabinet power supply failure
11/08/2023
Add PPC points for PZR PORV/Safety Tailpipe Temps and
Rate of Change
2/19/2023
Adjust Refueling Water Storage Tank Low Setpoint
2/15/2024
Hour Lost Time Due to ECCS Reset Buttons Not
Functioning
05/14/2024
OA WS Pump Stator Temperature Reaches Alarm Setpoint
05/20/2024
Must reset MST With Each IC Reset To Prevent Partial
Simulator Failure
08/07/2024
Exam Related
09/06/2024
STC Simulator Firewall Ruleset Consolidation
10/03/2024
H2 Temperature Meter Sticking
01/30/2025
SG 1A/1B WR SGWL Yokogawa Fails Intermittently
03/24/2025
Work Orders
Add PPC Alarm for Feedwater Regulating Valves
06/25/2025
Procedure Use and Adherence
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
Procedures
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
4815722
2A MSIV Air Pump Regulator Seems to be Degraded
11/06/2024
27290
MSIV Air Regulator Trend
01/03/2025
4837397
1AF005F in Mid Position Following Stroke from RSDP
2/14/2025
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
Corrective Action
Documents
4876951
2D MSIV Air Pump Regulator Degraded
06/27/2025
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
1BwOSR
3.6.3.5.AF-1B
Unit One Train B Auxiliary Feedwater Valve Stroke
Surveillance
Conduct of Equipment Reliability Manual
Procedures
Parts Quality Initiative (PQI)
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
Initial RICT Record for 1PT-0545 and 1B OTDT requires
Calibration
08/01/2025
Miscellaneous
Final RICT Record for 1P-0545 and 1B OTDT Requires
Calibration
08/05/2025
Procedures
Risk Informed Completion Time
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
Engineering
Evaluations
DG Closed System Leak Guidance (Lube Oil, Jacket Water,
and Fuel Oil)
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
Engineering
Changes
643635
Appendix J Local Leak Rate Scope Reduction -
Penetrations P-1, P-16, and P-41
Miscellaneous
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
24693
Fuel Transition Impact: 18 Month PR NIs Surveillance
Timing
2/18/2024
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
Fuel Pool Cooling System
E
1BwOSR 0.1-
1,2,3
Unit One Modes 1, 2, and 3 Shiftly and Daily Operating
Surveillance
104
Procedures
Ultrasonic (UT) Measurement of Material Thickness and
Interfering Conditions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1835382
1N-NR4083 Replace All Power Supplies
08/14/2025
21862
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
20055
Unexpected Annunciator 1VD01JA-1-A6
09/11/2025
04417340
1st Quarter 2021 Radiochemistry Crosscheck
04/18/2021
04483926
21 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
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
Radioactive Effluent and Environmental Monitoring
Programs
Radiological Environmental Monitoring Program
Radiological Environmental Monitoring Program and
Meteorological Program Implementation
Environmental Dosimetry - Performance Specifications,
Testing, and Data Analysis
Quality Assurance for Radiological Monitoring Programs
CY-BR-170-301
Offsite Dose Calculation Manual
Procedures
Radiological Groundwater Protection Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiological Groundwater Protection Program
Implementation
Self-Assessments NOSA-BRW-23-
Chemistry, Radwaste, Effluent and Environmental
Monitoring Audit Report
04/05/2023
Corrective Action
Documents
Resulting from
Inspection
NRC ID: No locks on Radioactive Materials Trailers
07/22/2025
DAW Ave
06/01/2022
DAW Ave
04/05/2024
DAW Ave
03/11/2025
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
Control of RAM Storage Areas and Containers Stored
Outside
Radioactive Material/Waste Shipments
Loading Dry Active Waste and Other Waste Forms for
Energy Solutions Waste Acceptance Guide (WAG-501)
CFR 61 Program
Process Control Program for Radioactive Wastes
Procedures
Process Control Program for Radioactive Wastes
Part 37 Implementation and Part 37 Security Plan
Compliance
01/15/2024
AR 04716439-01-
Radioactive Solid Waste Processing and Radioactive
Material Handling, Storage, and Transportation
11/08/2024
Self-Assessments
Part 37 Implementation and Part 37 Security Plan
Compliance
2/10/2025
Shipping Records
Radioactive
Waste Shipment
Number RWS24-
014
Resin Liner in Cask RT-100
2/23/2024
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
Monthly Data Elements for NRC ROP Indicator -
Reactor Coolant System (RCS) Specific Activity
various
Monthly Data Elements for NRC ROP Indicator -
Occupational Exposure Control Effectiveness
various
71151
Miscellaneous
Monthly Data Elements for NRC ROP Indicator -
RETS/ODCM Radiological Effluent Occurences
various
4101654
Trend 7300 NAL Cards
2/07/2018
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
Procedures
BwISR 3.3.1.10-
M239
Operational Test and Channel Verification / Calibration for
LOOP P-0457, Pressurizer Pressure Protection Channel III
Cabinet 3
2