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List of results

• 05000289/LER-1983-041-99, /99X-0:on 831025,while in Cold Shutdown,Cracking Observed on Molded Rubber Seat Ring of Containment Purge Isolation Valve AH-V1B.Caused by Insufficient Adhesion Between Plies of Seat Matl  + (/99X-0:on 831025,while in Cold Shutdown,Cracking Observed on Molded Rubber Seat Ring of Containment Purge Isolation Valve AH-V1B.Caused by Insufficient Adhesion Between Plies of Seat Matl)
• 05000331/LER-1983-041-99, /99X-0:on 831028,following Scram,Rcic Would Not Manually Trip.Solenoid Repaired & Reinstalled  + (/99X-0:on 831028,following Scram,Rcic Would Not Manually Trip.Solenoid Repaired & Reinstalled)
• 05000368/LER-1983-050-99, /99X-0:on 831109,diesel Generator 2 Exhibited Erratic Performance.Caused by Bad Contacts on Droop Relay in Conjunction W/Less than Optimum Tuning of Governor Controls.Droop Relay Replaced  + (/99X-0:on 831109,diesel Generator 2 Exhibited Erratic Performance.Caused by Bad Contacts on Droop Relay in Conjunction W/Less than Optimum Tuning of Governor Controls.Droop Relay Replaced)
• 05000272/LER-1983-062-99, /99X-0:on 831122,triaxial time-history Accelograph Inside Bioshield on 81-ft Elevation of Containment Bldg Failed.Cause Not Stated.Accelerometer Will Be Replaced During Next Outage  + (/99X-0:on 831122,triaxial time-history Accelograph Inside Bioshield on 81-ft Elevation of Containment Bldg Failed.Cause Not Stated.Accelerometer Will Be Replaced During Next Outage)
• 05000338/LER-1978-026-99, /99X-1 on 780413:with All Rods Out at Beginning of Core Life,Hot Zero Pwr Moderator Temp Coefficient Revealed It Was More Positive than 0 Delta K/K/F in Tech Spec,Due to Positive Mtc for the all-rods-out Configuration  + (/99X-1 on 780413:with All Rods Out at Beginning of Core Life,Hot Zero Pwr Moderator Temp Coefficient Revealed It Was More Positive than 0 Delta K/K/F in Tech Spec,Due to Positive Mtc for the all-rods-out Configuration)
• 05000338/LER-1978-061-99, /99X-1 on 780712:the Area Temp Monitoring Log Erroneously Recorded Excessive Temps in Battery Rooms.Cause Is Unknown  + (/99X-1 on 780712:the Area Temp Monitoring Log Erroneously Recorded Excessive Temps in Battery Rooms.Cause Is Unknown)
• 05000213/LER-1979-001-99, /99X-1 on 790214:Updates RO 79-01/IT on 790228 Re Batch 8 Fuel Failures.Most Defective Assemblies Removed from Core.Cause of Fuel Failure Still Unknown. Discusses Status of Current & Planned Investigations  + (/99X-1 on 790214:Updates RO 79-01/IT on 790228 Re Batch 8 Fuel Failures.Most Defective Assemblies Removed from Core.Cause of Fuel Failure Still Unknown. Discusses Status of Current & Planned Investigations)
• 05000346/LER-1978-066-99, /99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2  + (/99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2)
• 05000313/LER-1980-040-99, /99X-1:on 801001,emergency Hatch Local Leak Rate Test Connections Found Uncapped,Causing Outer Door to Be Bypassed by 3/4-inch Connection.Cause Not Stated.Caps Replaced & Test Procedures Revised  + (/99X-1:on 801001,emergency Hatch Local Leak Rate Test Connections Found Uncapped,Causing Outer Door to Be Bypassed by 3/4-inch Connection.Cause Not Stated.Caps Replaced & Test Procedures Revised)
• 05000272/LER-1981-060-99, /99X-1:on 810611,diesel Fire Suppression Pump 2 Failed to Start in Automatic Mode.Caused by Shearing Off of Drive Shaft Counterweight Gear.Shaft Replaced  + (/99X-1:on 810611,diesel Fire Suppression Pump 2 Failed to Start in Automatic Mode.Caused by Shearing Off of Drive Shaft Counterweight Gear.Shaft Replaced)
• 05000416/LER-1982-008-99, /99X-1:on 820626,during Testing of Carbon Dioxide (CO2) Fire Protection Sys,Ventilation Dampers for Div 1 & 2 Switchgear Rooms Failed to Close Upon CO2 Actuation Signal. Caused by Insufficient Power Supply to Melt Thermal Li  + (/99X-1:on 820626,during Testing of Carbon Dioxide (CO2) Fire Protection Sys,Ventilation Dampers for Div 1 & 2 Switchgear Rooms Failed to Close Upon CO2 Actuation Signal. Caused by Insufficient Power Supply to Melt Thermal Links)
• 05000416/LER-1982-021-99, /99X-1:on 820720,limiting Condition for Operation Entered Due to Quarterly Test of Radioactive Liquid Effluent Monitoring Sys Not Being Performed by 820720.Caused by Inadequate Sys Design.Design Change Implemented  + (/99X-1:on 820720,limiting Condition for Operation Entered Due to Quarterly Test of Radioactive Liquid Effluent Monitoring Sys Not Being Performed by 820720.Caused by Inadequate Sys Design.Design Change Implemented)
• 05000416/LER-1982-033-99, /99X-1:on 820814,HPCS Diesel Generator 13 Started on Low Reactor Vessel Level Indication & Tripped on Overspeed.Caused by Faulty Tachometer Relay.Dynalco Relay Replaced & Sys Restored on 820818  + (/99X-1:on 820814,HPCS Diesel Generator 13 Started on Low Reactor Vessel Level Indication & Tripped on Overspeed.Caused by Faulty Tachometer Relay.Dynalco Relay Replaced & Sys Restored on 820818)
• 05000416/LER-1982-063-99, /99X-1:on 820902,during Shutdown,Several fire- Rated Cable Penetration Seals Were Broken on Field Termination Cabinets in Control Room to Allow Routing of Addl Cable.Seals Repaired Following Maint Activities  + (/99X-1:on 820902,during Shutdown,Several fire- Rated Cable Penetration Seals Were Broken on Field Termination Cabinets in Control Room to Allow Routing of Addl Cable.Seals Repaired Following Maint Activities)
• 05000416/LER-1982-071-99, /99X-1:on 820903,smoke Detectors in Fire Zones 2-4,1-18 & 1-23 Alarmed W/No Fire or Fumes Present.Cause Not Stated.Detectors Cleaned & Returned to Svc.Zones 1-18 & 1-23 Alarmed Again on 820929.Fire Watch Established  + (/99X-1:on 820903,smoke Detectors in Fire Zones 2-4,1-18 & 1-23 Alarmed W/No Fire or Fumes Present.Cause Not Stated.Detectors Cleaned & Returned to Svc.Zones 1-18 & 1-23 Alarmed Again on 820929.Fire Watch Established)
• 05000416/LER-1982-123-99, /99X-1:on 821102,fire Barrier Penetrations to Cabinets in Control Bldg Broken to Complete Planned Maint Activity.Fire Watch Established.Penetrations Resealed. Limiting Conditions for Operation Cleared  + (/99X-1:on 821102,fire Barrier Penetrations to Cabinets in Control Bldg Broken to Complete Planned Maint Activity.Fire Watch Established.Penetrations Resealed. Limiting Conditions for Operation Cleared)
• 05000295/LER-1979-044-99, /99x-0 on 790608:operators Manually Initiated Safety Injection After False Steam Pressure Differential Signals Caused Control Room Safety Injection Annunciation. Caused by Waterhammer Shock in Steam Generator Loop D  + (/99x-0 on 790608:operators Manually Initiated Safety Injection After False Steam Pressure Differential Signals Caused Control Room Safety Injection Annunciation. Caused by Waterhammer Shock in Steam Generator Loop D)
• 05000320/LER-1980-001-99, /99x-0:on 800126,during Mode 5 operation,60 Amp Molded Case Circuit Breaker for Generator Auxiliaries Found Tripped.Caused by Defective Internal Connection on a Phase.Breaker Was Replaced  + (/99x-0:on 800126,during Mode 5 operation,60 Amp Molded Case Circuit Breaker for Generator Auxiliaries Found Tripped.Caused by Defective Internal Connection on a Phase.Breaker Was Replaced)
• ML013120433  + (/Braidwood, Units 1 and 2 - Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzle)
• ML021040008  + (/Braidwood, Units 1 and 2 - License Amendment, Revising Surveillance Requirement 3.0.3 to Extend the Delay Period, Before Entering a Limiting Condition for Operation, Following a Missed Surveillance)
• ML031070343  + (/Data Cover Sheet)
• 05000277/LER-1979-027, /O3L-0 on 790521:reactor Water Cleanup Inboard Isolation Valve Failed to Automatically Isolate in Test. Caused by Misaligned Limit Switch on Valve.Switch Adjusted & Maint Procedure Strengthened  + (/O3L-0 on 790521:reactor Water Cleanup Inboard Isolation Valve Failed to Automatically Isolate in Test. Caused by Misaligned Limit Switch on Valve.Switch Adjusted & Maint Procedure Strengthened)
• 05000278/LER-1979-014, /O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement  + (/O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement)
• 05000278/LER-1979-015, /O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc  + (/O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc)
• 05000277/LER-1979-029, /O3L-0 on 790524:firewatch Patrol Was Not Conducted While Fire Detection Sys Was Out of Svc for Const. Caused by Failure in Communications.Procedures Changed  + (/O3L-0 on 790524:firewatch Patrol Was Not Conducted While Fire Detection Sys Was Out of Svc for Const. Caused by Failure in Communications.Procedures Changed)
• 05000263/LER-1983-012, /O3L-0:on 830519,mode Switch Scram Bypass Annunciator Came on Following Energization of Reactor Protection Logic.Caused by Relay Race.Relays Manually Actuated to Return to Normal Condition  + (/O3L-0:on 830519,mode Switch Scram Bypass Annunciator Came on Following Energization of Reactor Protection Logic.Caused by Relay Race.Relays Manually Actuated to Return to Normal Condition)
• ML15251A381  + (/Quad Cities Nuclear Power Station, Units 1 and 2 - Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel)

• ML20134J986  + (/Unit 2 Fuel Assembly Insp Program)
• ML20134J984  + (/Unit 2 Fuel Assembly Insp Program)
• ML20134J978  + (/Unit 2 Fuel Assembly Insp Program)
• ML20134J960  + (/Unit 2 Fuel Assembly Insp Program)

• SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program  + (0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program)
• ML20224A224  + (0 E-Mail DOE-ORO Comments on Cyber Security Plan for Centrus Tmc - Public)
• ML24240A118  + (0 Issuance Letter Amendment 18 to Renewed Certificate of Compliance No. 1014 for the HI-STORM 100 Cask System)
• 05000244/LER-2002-001  + (0 LER 2002-001, Loss of "A" Condenser Circulating Water Pump Results in)
• ML21252A520  + (0 Updated Final Safety Analysis Report, Chapter 9, Figures (Redacted))
• ML24095A040  + (0 User Need Rulemaking Memo for HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewed Amendment No. 18)
• 05000413/LER-2013-001, 0 for Catawba Nuclear Station, Unit 1 and 2 Regarding Each Diesel Generator Was Determined to Be Unknowingly Inoperable During Its Monthly Surveillance Test Due to Technical Specification Surveillance Requirement 3.8.1.17 Not B  + (0 for Catawba Nuclear Station, Unit 1 and 2 Regarding Each Diesel Generator Was Determined to Be Unknowingly Inoperable During Its Monthly Surveillance Test Due to Technical Specification Surveillance Requirement 3.8.1.17 Not Being Met)
• 05000366/LER-2012-001, 0 for Edwin I. Hatch Nuclear Plant, 2B Standby Gas Treatment Filter Train Found Operating at Higher Flow than Allowed by Technical Specification  + (0 for Edwin I. Hatch Nuclear Plant, 2B Standby Gas Treatment Filter Train Found Operating at Higher Flow than Allowed by Technical Specification)
• 05000301/LER-2007-007, 0 for Point Beach Nuclear Plant Unit 2, One Overpower Delta T Channel Setpoint Outside Technical Specification Allowed Value  + (0 for Point Beach Nuclear Plant Unit 2, One Overpower Delta T Channel Setpoint Outside Technical Specification Allowed Value)
• 07200041/LER-2018-002, 0 for San Onofre Nuclear Generating Station ISFSI Re Spent Nuclear Fuel Transport Conveyance Vehicle Operated Outside Obstacle Clearance Limit  + (0 for San Onofre Nuclear Generating Station ISFSI Re Spent Nuclear Fuel Transport Conveyance Vehicle Operated Outside Obstacle Clearance Limit)
• 05000499/LER-2019-002, 0 for South Texas Project Unit 2, Incorrect Sequencer Part Replacement Leads to Undervoltage Signal and Valid Actuation of Emergency Diesel Generator  + (0 for South Texas Project Unit 2, Incorrect Sequencer Part Replacement Leads to Undervoltage Signal and Valid Actuation of Emergency Diesel Generator)
• 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications  + (0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications)
• ML20262H033  + (0 of Certificate of Compliance No. 9225 for the Model No. NAC-LWT Package)
• ML22021A855  + (0 of the ANO Security Plan)
• L-MT-03-072, 0 to A.2-807, Off-Site Dose Assessment and Protective Action Recommendations  + (0 to A.2-807, Off-Site Dose Assessment and Protective Action Recommendations)
• ML14337A687  + (0 to Arkansas Nuclear One, Units 1 and 2 Emergency Plan)
• ML20049J861  + (0 to CE-1-A, QA Program for Nuclear Generating Stations)
• ML20195B389  + (0 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models)
• ML20148S464  + (0 to Catawba Unit 1 Cycle 10 COLR for May 1997)
• ML20141C809  + (0 to Cycle 6 Colr)
• ML040340702  + (0 to EIP-ZZ-C0010, Revision 32 to EIP-ZZ-00102, and Revision 33 to EIP-ZZ-00240)
• ML17265A546  + (0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required)
• ML031920279  + (0 to EP-PS-106, Health Physics Specialist (Duty Foreman): Emergency Plan-Position Specific Procedure)