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FOIA-2025-000406 Released Set 2
	ML25091A047
Person / Time
Issue date:	03/27/2025
From:	; NRC/OCIO
To:	;
Shared Package
ML25091A043	List: ML25091A044; ML25091A045; ML25091A046; ML25091A047;
References
	FOIA-2025-000406
	Download: ML25091A047 (12)
	v • d • e

Item Title PIM Date Site Name Failure to Implement Preventive Maintenance Testing on DC Breakers 12/31/24 Braidwood Target Set Evaluation 11/21/24 Braidwood Vital Area 31 Day Access Review and Approval/Reapproval 11/21/24 Braidwood Automatic Reactor Trip Due to Steam Generator Low Flow Feedwater Isolation Valves Being Closed 9/30/24 Braidwood Failure to Perform Quality Review for NRC Information Notice 2017-06 6/30/24 Braidwood Failure to Implement Cyber Controls on Level 3/4 Firewall 2/7/24 Braidwood Licensee Failure to Implement Vulnerability Management Program 2/7/24 Braidwood Contamination of Auxiliary Feedwater (AF) Pump Diesel Engine Lubricating Oil 1/17/24 Braidwood Operation of the Main Steam (MS) System in a Manner Inconsistent with its Design 9/30/23 Braidwood Failure to Follow Steam Generator Eddy Current Testing Analysis Procedure 6/30/23 Braidwood Failure to Follow 1A Emergency Diesel Generator Maintenance Work Instructions 3/31/23 Braidwood (OUO-SRI) Green NCV - Target set equipment that could lead to radiological sabotage was inadequately protected 9/22/22 Braidwood Failure to Implement Cyber Security Controls 5/23/22 Braidwood Emergency Diesel Generator Voltage and Frequency Acceptance Criteria Incorrectly Translated to Surveillance Test Procedures 5/10/22 Braidwood Failure to Test Manual Valve Closure Function in Accordance with American Society of Mechanical Engineers Code 5/10/22 Braidwood Inadequate Work Instructions for Disassembly/Reassembly of Safety Injection (SI) Cold Leg Throttle Valve 3/31/22 Braidwood Simultaneous Inoperability of Both Trains of the Control Room Temperature Control System Resulting in a Loss of Safety Function 12/31/24 Byron Target Set Evaluation 12/16/24 Byron Vital Area 31 Day Access Review and Approval/Reapproval 11/19/24 Byron Failure to establish a time-based preventative maintenance schedule for Diesel Generator Ventilation Fans 9/30/24 Byron Failure to Satisfy ASME Code Case N-722-1 Examination Requirements for Reactor Coolant System (RCS) Pressure Boundary Welds 9/30/24 Byron Failure to Establish Adequate Work Instructions During 2A Emergency Diesel Generator Maintenance Resulting in Additional Repairs and Unavailability Time Due to Rocker Arm Lifter Failure 6/30/24 Byron Failure to Implement External Surfaces License Renewal Commitments as Described in the UFSAR.

6/28/24 Byron

Failure to follow System and Services Acquisition Policy and Procedures 3/5/24 Byron Failure to Correctly Translate Essential Service Water Design Basis into Procedures 2/29/24 Byron Failure to Translate Coupling Float Design Parameters into Maintenance Procedures 2/25/24 Byron Failure to Evaluate the Essential Service Water Pump Maximum Break Horsepower Requirement in the Protective Relay Settings for the Motor 2/23/24 Byron Failure to Follow Procedure to Maintain the Unit 2A Essential Service Water Pump and Motor Coupling within Specification 2/23/24 Byron Failure to Perform Required Inservice Testing of 1(2)SX007 Valves in Accordance with Code Requirements 2/23/24 Byron Failure to Perform Quality Review for NRC Information Notice 2017-06 2/16/24 Byron 0A Control Room Ventilation Inoperable due to Jumpers left on 0PR031J and 0PR032J (LER No. 454-2023-001-00 and 454-2023-001-01) 9/30/23 Byron Failure to Perform ASME Relief Valve Scope Expansion Testing as Required by Procedure 9/8/23 Byron Failure to Conduct One-Time Qualified Selective Leaching Examinations for License Renewal 3/31/23 Byron Failure to Establish a Preventive Maintenance Schedule to Replace Solenoid Valve 1CV8116 Prior to the End of its Specific Lifetime 12/20/22 Byron Failure to Use Correct Valve Factors to Ensure Motor Operated Valves Continued to be Capable of Performing Their Design Basis Functions 12/20/22 Byron Failure to Have Appropriate Work Instructions Leads to Inoperability of the Unit 1 Diesel Driven Auxiliary Feedwater Pump 6/30/22 Byron Failure to Adhere to Plant Barrier Control Program Leads to a Failure to Enter Technical Specification Limiting Condition of Operation 3.8.1.F for Two Diesel Generators Inoperable 3/31/22 Byron Failure to Follow Surveillance Procedure Leads to Actuation of Carbon Dioxide Suppression System in Opposite Unit 3/31/22 Byron Surveillance Test Procedure Inappropriate to the Circumstances Resulting in RCIC Turbine Trip 12/31/24 Clinton Failure to Establish Procedure Controls to Perform Commercial Grade Dedication Activities of Components Installed on Safety Related Equipment 8/30/24 Clinton Failure to Provide Switchyard Maintenance Oversight Led to Reactor Scram 12/31/23 Clinton Failure to Complete a Timely Operability Evaluation of a Deficient Condition Affecting the Division 2 Emergency Diesel Generator 6/30/23 Clinton Failure to Manage Risk During Emergency Reserve Auxiliary Transformer Maintenance 3/31/23 Clinton Failure to Perform Radioactive Effluent Sampling Required by the Offsite Dose Calculation Manual 9/30/22 Clinton Protective Features of Emergency Reserve Auxiliary Transformer Not Fully Translated to Procedures and Training 9/30/22 Clinton Failure to Correct a Non Conservative Technical Specification 5/5/22 Clinton Failure to Follow Procedure When Implementing ASME Code Case N-513-4 for Through-Wall Flaw 5/5/22 Clinton

Failure to Implement Seismic Requirements for Portable Equipment 9/30/24 Dresden Vital Area 31 Day Access Review and Approval/Reapproval 8/8/24 Dresden 2/3 Emergency Diesel Generator Output Breaker Opened During Surveillance Testing 6/30/24 Dresden Failure to Follow Procedure Resulting in Voiding in Unit 2 High Pressure Coolant Injection System 6/30/24 Dresden Failure to Properly Implement Fire Impairment Procedure 6/30/24 Dresden Fire Barrier Impaired 6/30/24 Dresden Failure to Install Safety-Related Circuit Breakers in the Unit 2 Alternate Battery, A Safety-Related System 9/30/23 Dresden Failure to perform performance response check for instrumentation 9/30/23 Dresden Failure to Correct Condition Adverse to Quality related to HPCI Instrument Uncertainty 8/4/23 Dresden Failure to Identify HPCI Signal Converter Lockout Function 8/4/23 Dresden Failure to Translate HPCI Room Design Basis Temperature into Surveillance Procedure 8/4/23 Dresden Failure to Implement Condensate System Startup Procedure 3/31/23 Dresden Failure to follow System and Services Acquisition Policy and Procedures 3/17/23 Dresden Unit 2 Firewall Syslog message 106015 was disabled 3/17/23 Dresden Failure to Have Procedure Adequate for the Circumstances for External Events 1/27/23 Dresden Failure to Perform an Analysis or Alternate Testing Method to Exempt As-Left Type C Testing on the Inboard MSIVs 1/27/23 Dresden Failure to Perform Vendor-Required Maintenance Checks on Emergency Diesel Generator Air System Air Line Lubricators 1/27/23 Dresden Failure to Screen and Prioritize Work To Correct A Degraded Condition With the 2/3 Cribhouse Trash Rake 1/27/23 Dresden Failure to Document and Maintain Target Set Created Operator Actions 10/21/22 Dresden Failure to Select Appropriate Packing for the Unit 3 1B Main Steam Isolation Valve 9/30/22 Dresden Failure to Document a Condition Adverse to Quality for the Unit 3 Main Power Transformer Control Power Cabinet Fire 3/31/22 Dresden Failure to Ensure That No Floatable Material Could Migrate Towards Floor Drains in Areas Containing Safety-Related Equipment 9/30/24 LaSalle Failure to Verify Proper Breaker Operation Results in an Undetected Misaligned Mechanically Operated Contact Switch 9/30/24 LaSalle Vital Area 31 Day Access Review and Approval/Reapproval 8/15/24 LaSalle Failure to Implement/Perform Two Cyber Security Controls after Access to Critical Digital Assets 7/25/24 LaSalle

Failure to Establish Acceptance Criteria for ECCS Service Water Strainer Inspections 5/3/24 LaSalle Failure to Follow Seismic Storage Requirements for a Temporary Battery Charger Stacked on an Unrestrained Cart Configuration Adjacent to the Safety-Related Unit 1 125Vdc Division 2 Battery Rack and Exposed Terminals 3/31/24 LaSalle Failure to Promptly Correct Degraded Pressure Switches in the Unit 1 and Unit 2 Main Steam Line High Flow Isolation Logic System 3/31/24 LaSalle Failure to Test Motor-Operated Valve in Accordance with the Inservice Test Program 3/31/24 LaSalle Failure to Use Calibrated Measuring and Test Equipment to Electrically Backseat a Safety Related Motor-Operated Valve 3/31/24 LaSalle Failure to Respond to the Attempted Introduction of Contraband to the Protected Area 3/24/24 LaSalle Failure to Comply With ASME Code Requirements Following Test Failure 12/15/23 LaSalle Failure to Ensure 'A' Train Main Control Room Ventilation Return Fan Breaker Instantaneous Trip Setpoint Set to Design Specifications 9/30/23 LaSalle Failure to Verify That Received Equipment Conformed With Procurement Documents, Resulting In an Internal Fire and LaSalle Unit 2 Manual Scram 9/30/23 LaSalle Failure to Assure Charpy V-Notch Impact Test Conformed to American Society of Mechanical Engineers (ASME)Section III 3/31/23 LaSalle Failure to Secure Category 2 Quantity of Radioactive Material not Under Direct Control and Constant Surveillance 3/31/23 LaSalle Failure to Determine Compliance with Technical Specification Surveillance Requirement 3.8.3.1 in Accordance With Procedure 10/17/22 LaSalle Failure to Incorporate Instrument Uncertainty Into Emergency Diesel Generator 7-Day Fuel Supply Surveillance Procedure 10/17/22 LaSalle Failure to Change Password after Access to Critical Digital Asset 8/5/22 LaSalle Failure to include a Software in the Cyber Security Baseline for Integrated Video Management System 8/5/22 LaSalle Failure to Correct a Condition Adverse to Quality 6/30/22 LaSalle Failure to Include Non-Safety Related Valve in 50.49 Program 6/30/22 LaSalle Preventative Maintenance Schedule Failed to Prevent an Age-Related Breaker Failure 3/31/22 LaSalle Failure to Correct Inadequate Jumper Cable Labeling Practices 10/3/24 Quad Cities Failure to Identify Condition Adverse to Quality Following a Corrective Action Program Evaluation of a Reactor Core Isolation Cooling Low Flow Event 10/3/24 Quad Cities Failure to Identify a Negative Low Safety Significant Trend in 10 CFR 50.65(a)(3) Periodic Assessment 9/30/24 Quad Cities Inadvertent Operation of Reactor Core Isolation Cooling System in an Unanalyzed Low-Flow Condition 9/30/24 Quad Cities Failure to Classify Components as Critical in Accordance with the Preventive Maintenance Program 9/17/24 Quad Cities

Failure to Identify and Correct Conditions Adverse to Quality Regarding the Installation of the Safety-Related 125 and 250 VDC Batteries Inter-Tier Jumper Cables.

9/17/24 Quad Cities Failure to Correct a Condition Adverse to Quality Following 10 CFR Part 50, Appendix J, Containment Local Leak Rate Testing 6/30/24 Quad Cities Inadequate Work Practices Result in Two FLEX Generators Having the Incorrect Phase Rotation Following Surveillance Testing 3/31/24 Quad Cities Inadvertent Disconnect of the Alternate 125 Vdc Battery during Surveillance Testing of the Normal 125 Vdc Battery 3/31/24 Quad Cities Inadvertent Isolation of the Reactor Core Isolation Cooling System due to Human Performance Error During Maintenance 3/31/24 Quad Cities Failure to Adequately Control Radiological Work 12/31/23 Quad Cities Failure to Implement a Preventive Maintenance Strategy for 2A Core Spray Flexible Rubber Cooling Line 12/31/23 Quad Cities Failure to Maintain Unit 1 Station Blackout Diesel in a Standby Lineup During Chemistry Sampling 12/31/23 Quad Cities Loss of Design Control on 2B Residual Heat Removal Pump Associated with a Nonconforming Flexible Rubber Cooling Line 12/31/23 Quad Cities Unit 2 Reactor Scram Due to Improperly Tuned Emergency Feedwater Heater Level Control Valve 12/31/23 Quad Cities Operator actions that can be disabled or prevented from a remote location 11/28/23 Quad Cities Discrepancies Between 250 VDC Calculations and Design Basis Acceptance Criteria Used in Test Procedures 11/16/23 Quad Cities Failure to Determine and Document Operability Associated with Technical Specification 3.2 Power Distribution Limits Following a Failure of the HPCI Flow Controller 11/16/23 Quad Cities Failure to Follow Procedural Instructions for Battery Installation 11/16/23 Quad Cities Non-conservative Valve Factor Used to Demonstrate Motor Operated Valve 1-1001-23A Continued to be Capable of Performing its Design Basis Safety Functions 11/16/23 Quad Cities Failure of the Unit 1 Station Blackout Diesel to Obtain Full Load 9/30/23 Quad Cities Failure to Correct a Condition Adverse to Quality Associated with a 4 kilovolt (kV) Breaker Fuse Block 9/30/23 Quad Cities Unit 2 SBO Breaker Failed to Close During Quarterly Surveillance 9/30/23 Quad Cities Inadequate Work Instructions for High-Pressure Coolant Injection Cooling Water Pressure Control Valve 6/30/23 Quad Cities Shift Staffing Below Minimum Technical Specifications 6/30/23 Quad Cities Failure to Adequately Implement and Review Auditable Events on the Kiosks 5/18/23 Quad Cities Inadequate Procedure for Feedwater System Failure 3/31/23 Quad Cities Licensee Operability Determination Procedure Inconsistent With Regulatory Requirements of 10 CFR 50.55a, "Codes and Standards" 12/31/22 Quad Cities

Failure to Follow Operations Procedures for Lowering Reactor Vessel Water Level 10/7/22 Quad Cities Failure to Identify and Correct a Condition Adverse to Quality Resulting in Both Trains of Standby Gas Treatment being Rendered Inoperable and Non-Functional 10/7/22 Quad Cities Failure to Incorporate Vendor Recommendations into Preventative Maintenance Procedures 10/7/22 Quad Cities Failure to Incorporate FLEX Time-Sensitive Actions into Site Procedures 9/30/22 Quad Cities Failure to Perform General Visual Examination of Accessible Surfaces of Containment Penetrations Required by Paragraph 10 CFR 50.55a(g)(4) 9/30/22 Quad Cities 02-0203-3B Electromatic Relief Valve Failed to Operate During As-Found Testing During Refueling Outage Q2R26 7/14/22 Quad Cities Failure to Identify a Condition Adverse to Quality During 2-0203-3B ERV Actuator Rebuild 6/30/22 Quad Cities Failure of High-Level Switch in HPCI Gland Seal Exhaust Condenser 3/31/22 Quad Cities Failure to Perform an Adequate Maintenance Risk Assessment during Corrective Maintenance Activities 3/31/22 Quad Cities

ML25091A047

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