Pages that link to "10 CFR 50.73(a)(2)(v), Loss of Safety Function"
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The following pages link to 10 CFR 50.73(a)(2)(v), Loss of Safety Function:
Displayed 50 items.
- 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release (← links)
- 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- 10 CFR 20.2201(a)(1)(i) (← links)
- 10 CFR 73.71(b)(1), Safeguards Event (← links)
- 10 CFR 35.3045(a)(3) (← links)
- 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation (← links)
- 10 CFR 35.3045(a)(1) (← links)
- 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(a)(1)(i), Emergency Class Declaration (← links)
- 10 CFR 50.72(b)(3)(iv)(A), System Actuation (← links)
- 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown (← links)
- 10 CFR 30.50(b)(2) (← links)
- 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness (← links)
- 10 CFR 20.2201(a)(1)(ii) (← links)
- 10 CFR 50.73(a)(1), Submit an LER (← links)
- 10 CFR 20.2202(b)(1) (← links)
- 10 CFR 40.35(f) (← links)
- 10 CFR 50.72(b)(3)(xii), Transport of a Contaminated Person Offsite (← links)
- 10 CFR 30.50(b)(1) (← links)
- 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge (← links)
- 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded (← links)
- 10 CFR 20.1906(d)(2) (← links)
- 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 76.120(c)(2) (← links)
- 10 CFR 40.60(b)(2) (← links)
- 10 CFR 40.60(b)(3) (← links)
- 10 CFR 26.719, FFD Reporting requirements (← links)
- 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect (← links)
- Agreement State (← links)
- NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73 (← links)
- 05000286/LER-2015-001, Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Level Alarms Due to Freezing of the Level Instrument Sensing Lines Caused by a Failed Strip Heater (← links)
- 10 CFR 50.73(a)(2)(iv)(A), System Actuation (← links)
- 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(b)(3)(v), Loss of Safety Function (← links)
- 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.73(a)(2)(v) (redirect page) (← links)
- 05000275/LER-2015-001, Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld (← links)
- 05000458/LER-2015-001, Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments (← links)
- 05000458/LER-2014-005 (← links)
- 05000368/LER-2013-002 (← links)
- 05000529/LER-2007-004 (← links)
- 05000529/LER-2002-002 (← links)
- 05000529/LER-2001-002 (← links)
- 05000529/LER-2001-001 (← links)
- 05000529/LER-2000-009 (← links)
- 05000529/LER-2000-008 (← links)
- 05000529/LER-2000-006 (← links)
- 05000529/LER-2000-005 (← links)
- 05000529/LER-2000-001 (← links)
- 05000446/LER-2010-001 (← links)
- 05000414/LER-2012-001 (← links)
- 05000528/LER-2007-006 (← links)
- 05000325/LER-2016-002 (← links)
- 05000323/LER-2010-001 (← links)
- 05000530/LER-2001-002 (← links)
- 05000530/LER-2001-001 (← links)
- 05000528/LER-2001-003 (← links)
- 05000528/LER-2001-002 (← links)
- 05000528/LER-2001-001 (← links)
- 05000423/LER-2001-004 (← links)
- 05000413/LER-2001-002 (← links)
- 05000382/LER-2001-002 (← links)
- 05000336/LER-2001-007 (← links)
- 05000328/LER-2003-001 (← links)
- 05000327/LER-2005-001 (← links)
- 05000321/LER-2001-001 (← links)
- 05000317/LER-2001-002 (← links)
- 05000306/LER-2001-003 (← links)
- 05000286/LER-2001-001 (← links)
- 05000278/LER-2001-001 (← links)
- 05000272/LER-2001-002 (← links)
- 05000272/LER-2001-001 (← links)
- 05000266/LER-2001-002 (← links)
- 05000220/LER-2001-002 (← links)
- 05000341/FIN-2016004-06 (← links)
- 05000331/FIN-2015004-03 (← links)
- 05000266/FIN-2013002-08 (← links)
- 05000456/FIN-2013002-11 (← links)
- 05000324/FIN-2013010-04 (← links)
- 05000387/FIN-2014005-03 (← links)
- 05000285/FIN-2015008-04 (← links)
- 05000387/FIN-2016001-02 (← links)
- 05000410/FIN-2016001-05 (← links)
- 05000317/FIN-2016002-02 (← links)
- 05000260/FIN-2016002-03 (← links)
- 05000390/FIN-2017002-04 (← links)
- 05000354/FIN-2015002-03 (← links)
- 05000254/LER-1994-002, Forwards LER 94-002,Rev 0 Re B CR HVAC Being Inoperable Due to Failure of Compressor Motor Contactor.Hot Gas Bypass Sys for Compressor Will Be Installed to Minimize Cycling by Inducing Larger Heat Load on Compressor (← links)
- 05000265/LER-1994-001, Forwards LER 94-001-00.IST Procedures Revised to Incorporate Interim Procedure Requirements & RCIC Pump Tested Using Revised Procedures (← links)
- 05000254/LER-1995-004, Forwards LER 95-004.Listed Commitments Made,Including Updating Vendor Technical Manual CO099, GE Protective Relays & Accessories (← links)
- 05000265/LER-1996-001, Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept (← links)
- 05000265/LER-1997-001, Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed (← links)
- 05000336/LER-1997-006, Forwards LER 97-006-00 Which Documents an Event That Occurred on 970211.Commitments Made within Ltr,Listed (← links)
- 05000423/LER-1996-044, Forwards LER 96-044-00,documenting Condition That Was Determined at Millstone Unit 3,on 961108.Commitments,encl (← links)
- 05000352/LER-1987-066, Forwards LER 87-066-00,correcting Date of Rept from 870107 to 880107 (← links)
- 05000254/LER-1997-009, Forwards LER 97-009-00 Per 10CFR50.73(a)(2)(v)(D).Commitment Included in Ltr (← links)
- 05000277/LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601 (← links)
- 05000336/LER-1997-015, Forwards LER 97-015-00 Per 10CFR50.73(a)(2)(v).Also Includes Commitments Made in Ltr (← links)
- 05000336/LER-1997-014, Forwards LER 97-014-00 Which Documents an Event That Occurred on 970415.Commitments Made within Ltr,Submitted (← links)
- 05000254/LER-1997-010, Forwards LER 97-010-00 Which Repts Event That Occurred at Quad Cities Nuclear Station,Per 10CFR50.73(a)(2)(v)(D). Commitment Made by Ltr,Submitted (← links)
- 05000254/LER-1997-005, Forwards LER 97-005-00 IAW Requirements of 10CFR50.73(a)(2)(v)(D) W/Listed Commitments (← links)
- 05000336/LER-1997-011, Forwards LER 97-011-00,documenting Event Occurred at Unit 2 on 970402.Commitments Made within Ltr Listed (← links)
- 05000254/LER-1997-008, Forwards LER 97-008,Rev 00 & Submits Commitments.Revised Qcop 2300-13 Is to Include Steps to Fully Disengage Turning Gear If Necessary for Testing Purposes (← links)
- 05000254/LER-1996-021, Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made (← links)
- 05000265/LER-1996-002, Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint (← links)
- 05000354/LER-1996-030, Submits List of Commitments Re Unplanned HPCI Sys Inoperability Due to Stuck Open Extended Containment Boundary Valve in LER 96-030-00 (← links)
- 05000354/LER-1996-028, Forwards LER 96-028-00,submitted Pursuant to Requirements of 10CFR50.73(a)(2)(v).Commitments Listed (← links)
- 05000265/LER-1996-003, Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted (← links)
- 05000423/LER-1996-046, Fowards LER 96-046-00.Licensee Commitments Listed,Including Containment Fuel Drop Radiation Monitor Design Reviewed & TS Change Request Will Be Submitted to NRC for Approval (← links)
- 05000254/LER-1996-020, Forwards LER 96-020-00.Commitments Included in LER & Submitted (← links)
- 05000423/LER-1996-032, Forwards LER 96-032-00 Re 960909 Event.Listed Commitments Will Be Completed Including Performance of Hydrostatic Test of Sih Relief Valves (← links)
- 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a (← links)
- 05000254/LER-1988-001, Sanitized Version of LER 88-001-00:on 880114,records Review Found Two Apparent Overexposures of Contractor Personnel During Fourth Quarter 1980.Caused by Inaccurate Secondary &/ or Primary Dosimetry.Dosimetry Sys Upgraded (← links)
- 05000336/LER-1997-034, Forwards LER 97-034-00 Which Documents Condition That Was Identified at Mnps,Units 2 on 971029.Commitments Made within Ltr Listed (← links)
- 05000333/LER-1997-010, Forwards LER 97-010-00 Re Surveillance Testing of Pressure Suppression Chamber.No Commitments Contained in Rept (← links)
- 05000352/LER-1997-009, Forwards LER 97-009-00 Which Documents Event That Occurred at Lgs,Units 1 & 2 on 971015 (← links)
- 05000304/LER-1997-003, Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B) (← links)
- 05000254/LER-1997-022, Forwards LER 97-022-00,per 10CFR50.73(a)(2)(v)(D).Commitment Stating That Qcos 5750-04 Will Be Enhanced by Adding Precautions for Opening of Bypass Valve & Verification That Relief Valve Has Not Lifted & Failed to Reseat,Listed (← links)
- 05000304/LER-1997-004, Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl (← links)
- 05000254/LER-1997-027, Forwards LER 97-027-00,per 10CFR50.73(a)(2)(v)(D). Commitments Made by Util,Listed (← links)
- 05000353/LER-1998-008, Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl (← links)
- 05000454/LER-1998-020, Forwards LER 98-020-00 IAW 10CFR50.73(a)(2)(v).Actions to Address Cause of Event Listed (← links)
- 05000289/LER-1999-001, Forwards LER 99-001-00,re Short Sections of Piping Were Below Temps Specified in FSAR Section 9.2.1.2.LER Is follow-up to Notification Made Via ENS Telephone to NRC on 990122 (← links)
- 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure (← links)
- 05000336/LER-1997-031, Forwards LER 97-031-00 Which Documents Event That Occurred at Mnps,Unit 2 on 970918.Commitments Made within Ltr Listed (← links)
- 05000155/LER-1998-001, Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B) (← links)
- 05000336/LER-1998-009, Forwards LER 98-009-00,documenting Event Which Occurred at Millstone Unit 3 on 980501.Commitments Made within Ltr,Encl (← links)
- 05000277/LER-1989-007, Corrected LER 89-007-00:on 890411,green Discoloration Discovered in Grease on Stabs of Control Fuses in Switchgear.Root Cause of Event Under Investigation.Stabs Lubricated W/Different Type of Approved Grease (← links)
- 05000277/LER-1989-006, Corrected LER 89-006-00:on 890209 & 25,determined That Tubing to Containment Isolation Valve Installed W/Inadequate Support & Containment Atmosphere Control & Dilution Sys Not Per Applicable Installation Criteria.Controls Estab (← links)
- 05000354/LER-1998-003, Forwards LER 98-003-00 Re Concurrent Inoperability of a & B Cr.Commitments Made by Pse&G,Encl (← links)
- 05000295/LER-1989-008, Forwards LER 89-008-00 Re Room Cooler Svc Water Supply Discrepancy Discovered on 890609 (← links)
- 05000267/LER-1987-019, Forwards LER 87-019-00 & 870911 Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment (← links)
- 05000220/LER-1997-015, Informs NRC That Util Is Retracting LER 97-015, Potential Bypass Leakage Path Between Drywell & Torus During Vent & Purge, Which Had Been Reported IAW 10CFR50.73(a)(2)(v)(D). Leakage Path Would Not Have Prevented Plant Function (← links)
- 05000301/LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics (← links)
- 05000339/LER-1989-003, Advises of Change in Reportability for LER 89-003-00 Re 10 Containment Isolation Valves W/Excessive Leak Rates (← links)
- 05000354/LER-1998-001, Forwards LER 98-001-00,re Missed HPCI Surveillance Resulting in Unavailability of HPCI (← links)
- 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form (← links)
- 05000275/LER-1986-012, Forwards LER 86-012-00 Re Inoperability of Both RHR Trains & Failure to Rept Event within Time Required.Event Did Not Affect Public Health & Safety (← links)
- 05000245/LER-1997-034, Forwards LER 97-034-00 Documenting Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 970812.Listed Commitments Made within Ltr (← links)
- 05000498/LER-1988-016, Forwards LER 88-016-00 in Response to NRC Re Violations Noted in Insp Rept 50-498/88-01 Concerning Feedwater Flow Transmitters.Violation Fully Addressed as LER Subj.Corrective Actions Completed & Reviewed by NRC (← links)
- 05000368/LER-1985-022, Corrects Forwarding LER 85-022-00.Unit,docket & License Number Incorrectly Listed on Cover Ltr 2CAN118503 (← links)
- 05000327/LER-2021-002, Letter Forwarding LER 2021-002-00 & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2 (← links)
- 05000374/LER-1991-009, Corrected Ltr Forwarding LER 91-009-00.Original Ltr Contained Error in Rept Number (← links)
- 05000315/LER-1999-027, LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination (← links)
- 05000346/LER-2021-001, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground (← links)
- 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor (← links)
- 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure (← links)
- 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System (← links)
- 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary (← links)
- 05000483/LER-2024-002, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (← links)
- 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground (← links)
- 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement (← links)
- 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function (← links)
- 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal (← links)
- 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection (← links)
- 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping (← links)
- 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators (← links)
- 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump (← links)
- 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000440/LER-2024-002, Reactor Water Clean Up Leak Detection Loss of Safety Function (← links)
- 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator (← links)
- 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications (← links)
- 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater (← links)
- 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation (← links)
- 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 (← links)
- 05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning (← links)
- 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water (← links)
- 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications (← links)
- 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure (← links)
- 05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) (← links)
- 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close (← links)
- 05000414/LER-2024-001, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan (← links)
- 05000366/LER-2024-001, High Pressure Coolant Injection (HPCI) System Inoperable (← links)
- 05000528/LER-2023-003, Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start (← links)
- 05000259/LER-2023-003, Standby Liquid Control Inoperable Due to Demineralized Water In-Leakage (← links)
- 05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation (← links)
- 05000499/LER-2023-001, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000339/LER-2023-001, Reactor Coolant Pressure Boundary Leak Due to Poor Weld Workmanship (← links)
- 05000498/LER-2023-003, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications (← links)
- 05000458/LER-2022-004-01, High Pressure Core Spray Inoperable Due to Transformer Failure (← links)
- 05000259/LER-2022-002-01, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator (← links)
- 05000445/LER-2023-001-01, (Cpnpp), Automatic Reactor Trip Due to Lo-Lo Steam Generator Level (← links)
- 05000315/LER-2023-001, Two Trains of Fuel Handling Area Exhaust Ventilation Inoperable (← links)
- 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low (← links)
- 05000445/LER-2023-001, Automatic Reactor Trip Due to Lo-Lo Steam Generator Level (← links)
- 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open (← links)
- 05000354/LER-2023-001, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable (← links)
- 05000373/LER-2023-001, Low Pressure Core Spray Inoperable Due to Minimum Flow Valve Flow Pressure Switch Failure (← links)
- 05000250/LER-2023-001, RCS Pressure Boundary Degraded (← links)
- 05000259/LER-2023-001-01, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm (← links)
- 05000498/LER-2023-001, Pressurizer Power Operated Relief Valve Failed to Open (← links)
- 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer (← links)
- 05000244/LER-2023-001, Vital Bus 17 Failed to Load Onto Emergency Diesel Generator B During Load / Safeguard Sequence Testing; Corroded Breaker Shunt Trip Attachment Plunger Found Which Indicated an Earlier Violation of Technical Specification 3.8.1 (← links)
- 05000387/LER-2023-002, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due Failure of the HPCI Turbine Stop Valve to Fully Close, Most Likely Due to Internal Corrosion and (← links)
- 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize (← links)
- 05000374/LER-2021-002-02, Supplement to Reactor Protection System Half Scram Due to Motor Generator Set Output Breaker Trip (← links)
- 05000458/LER-2023-001, Ultimate Heat Sink Inoperable Due to Boundary Valve Leakage (← links)
- 05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications (← links)
- 05000440/LER-2023-002, Main Steam Line Leakage Exceeded Technical Specification Limit (← links)
- 05000366/LER-2023-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) (← links)
- 05000259/LER-2023-001, High Pressure Coolant Injection System Inoperable Due to a Torn Valve Diaphragm (← links)
- 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors (← links)
- 05000373/LER-2022-004, Both Trains of Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Compressor Trips (← links)
- 05000373/LER-2022-003-02, Supplement to Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000483/LER-2022-003, Submittal of Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications (← links)
- 05200025/LER-2022-002, Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes (← links)
- 05000416/LER-2022-002, Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage (← links)
- 05000327/LER-2022-002, Turbine Trip Function Inoperable Due to Slow to Close Turbine Throttle Valve (← links)
- 05000352/LER-2022-001, Regarding HPCI Inoperable Due to Inadvertent Isolation Signal (← links)
- 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low (← links)
- 05000416/LER-2021-001-01, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate (← links)
- 05000388/LER-2022-001, Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable (← links)
- 05000458/LER-2022-004, High Pressure Core Spray Inoperable Due to Transformer Failure (← links)
- 05000382/LER-2022-006, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors (← links)
- 05000445/LER-2022-001, (Cpnpp), Reactor Trip Due to Turbine Trip Greater than 50% Power (← links)
- 05000335/LER-2022-003, Manual Reactor Trip Due to Loss of Feedwater Pump (← links)
- 05000335/LER-2022-002, Condition Prohibited by Technical Specifications (← links)
- 05000528/LER-2022-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses (← links)
- 05000373/LER-2022-003-01, Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000259/LER-2022-002, High Pressure Coolant Injection System Declared Inoperable Due to a Corroded Actuator (← links)
- 05000325/LER-2022-001, High Pressure Coolant Injection (HPCI) Inoperable (← links)
- 05000412/LER-2022-001, Operation or Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Fuel Oil Intrusion Into Lube Oil (← links)
- 05000254/LER-2022-003, Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line (← links)
- 05000458/LER-2022-003, Division 1 Standby Diesel Generator Speed Sensor Power Supply Failure (← links)
- 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23 (← links)
- 05000369/LER-2022-001, Both Control Room Area Chilled Water System Trains Inoperable Due to Human Error (← links)
- 05000440/LER-2022-001, Low Pressure Core Spray Inoperable Due to Loss of Minimum Flow Valve (← links)
- 05000373/LER-2022-003, Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000530/LER-2021-001-01, Reactor Trip During Control Element Assembly Alignment Activities (← links)
- 05000263/LER-2022-001, Loss of Control Room Envelope Operability (← links)
- 05000254/LER-2022-002, Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue (← links)
- 05000259/LER-2021-001-01, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay (← links)
- 05000341/LER-2022-002, Unexpected High Pressure Coolant Injection Turbine Trip (← links)
- 05000287/LER-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve (← links)
- 05000529/LER-2022-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses (← links)
- 05000333/LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure (← links)
- 05000397/LER-2021-002-01, Integrated Leak Rate Test (← links)
- 05000528/LER-2021-001-01, Unit 1 and 3 Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses (← links)
- 05000374/LER-2022-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation (← links)
- 05000382/LER-2022-002, Operation Prohibited by Technical Specifications Due to Personnel Error (← links)
- 05000270/LER-2022-003, Manual Reactor Trip Due to Main Feedwater Control Valve Positioner Malfunction (← links)
- 05000270/LER-2022-001, Regarding Automatic Reactor Trip Due to Loss of Power to Reactor Coolant Pumps (← links)
- 05000287/LER-2022-001, Response Actions Resulted in Brief Inoperability of Both Onsite and Offsite Emergency AC Power Paths (← links)
- 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000341/LER-2021-002-01, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure (← links)
- 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly (← links)
- 05000270/LER-2021-005, Automatic Reactor Trip Due to Spurious Trip Signal Concurrent with System Testing (← links)
- 05000388/LER-2021-002-01, Loss of Secondary Containment Due to Failed Differential Pressure Transmitter (← links)
- 05000270/LER-2021-004, More than One Axial Power Shaping Rod Not Aligned within Technical Specification Limits (← links)
- 05000270/LER-2021-003, Conditions Prohibited by Technical Specifications Due to Ssf and Psw Inoperability (← links)
- 05000335/LER-2021-001, Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators (← links)
- 05000530/LER-2021-001, Reactor Trip During Control Element Assembly Alignment Activities (← links)
- 05000529/LER-2021-002-01, Reactor Trip During Plant Protection System Surveillance Testing (← links)
- 05000270/LER-2021-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 2 Main Feeder Buses (← links)
- 05000254/LER-2022-001, Regarding High Pressure Coolant Injection System Inoperable Due to Gland Seal System Malfunction (← links)
- 05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure (← links)
- 05000341/LER-2021-003, High Pressure Coolant Injection Inoperable Due to Contact Oxidation (← links)
- 05000458/LER-2021-005, Potential Loss of Safety Function Due to Inoperable Reactor Core Isolation Cooling Steam Flow Transmitter (← links)
- 05000328/LER-2021-001, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency (← links)
- 05000528/LER-2021-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Bus (← links)
- 05000397/LER-2021-002, Integrated Leak Rate Test (← links)
- 05000259/LER-2021-001, Volt Load Shed Logic Inoperable Longer than Allowed by Technical Specifications Due to Failed Relay (← links)
- 05000352/LER-2021-001, HPCI Inoperable Due to Remote Shutdown Panel Switch Failure (← links)
- 05000389/LER-2021-002, Foreign Material Exclusion Device Found in Containment Spray System (← links)
- 05000416/LER-2021-003, High Pressure Core Spray Declared Inoperable (← links)
- 05000321/LER-2021-003, High Pressure Coolant Injection System Discharge Valve Failure to Open (← links)
- 05000388/LER-2021-002, Re Loss of Secondary Containment (← links)
- 05000341/LER-2021-002, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure (← links)
- 05000327/LER-2021-003, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable (← links)
- 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip (← links)
- 05000397/LER-2021-001, Breach of Secondary Containment (← links)
- 05000323/LER-2021-001, Emergency Diesel Generator Declared Inoperable Due to Low Frequency Condition Discovery During Routine Surveillance (← links)
- 05000333/LER-2020-003-01, High Pressure Coolant Injection Inoperable Due to Oil Leak (← links)
- 05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000316/LER-2024-004, AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications (← links)
- 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram (← links)
- 05000416/LER-2020-003-01, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram (← links)
- 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip (← links)
- 05000255/LER-2021-001, Atmospheric Steam Dump Valves Inoperable Due to Relay Failure (← links)
- 05000446/LER-2021-001, Reactor Trip Due to Fault on Main Transformer 2MT1 (← links)
- 05000414/LER-2021-003, Re Containment Penetration Failure Resulting in Integrated Leak Rate Test Failure (← links)
- 05000327/LER-2021-001, Sequoya Nuclear Plant, Unit 1, Reactor Trip on High Neutron Flux Rate Due to Dropped Control Rods (← links)
- 05000529/LER-2021-002, Reactor Trip During Plant Protection System Surveillance Testing (← links)
- 05000341/LER-2021-001, Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis (← links)
- 05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment (← links)
- 05000387/LER-2018-005-02, (SSES) Unit 1 Re Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000387/LER-2017-010-02, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000387/LER-2021-002, Inoperability of Computer Room Floor Cooling Fan Caused by Extended Operation with Worn Belts Due to Less than Adequate Preventive Maintenance Replacement Interval (← links)
- 05000277/LER-2021-001, High Pressure Coolant Injection System Declared Inoperable Due to Instrument Power Inverter Failure (← links)
- 05000461/LER-2020-003, Reactor Core Isolation Cooling System Card Fuse Failure Results in a Condition Prohibited by Technical Specifications and That Could Have Prevented Fulfillment of a Safetv Function Needed to Control (← links)
- 05000416/LER-2021-001, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate (← links)
- 05000440/LER-2020-002-01, Standby Liquid Control System Rendered Inoperable Due to Valve Misposition (← links)
- 05000387/LER-2021-001, Electri Station, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due to a Primary Containment Isolation (PCIV) Valve Failure to Stroke Full Closed On-demand Due to an Intermittent Break (← links)
- 05000529/LER-2021-001, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps (← links)
- 05000318/LER-2021-001, Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking (← links)
- 05000390/LER-2021-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000298/LER-2021-001, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications (← links)
- 05000483/LER-2021-001, Manual Actuation of Essential Service Water System (← links)
- 05000389/LER-2021-001, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center (← links)
- 05000461/LER-2020-002, Simultaneous Lnoperability of Main Control Room Ventilation Subsystems a and B (← links)
- 05000416/LER-2019-006-01, Failure to Meet Technical Specification 5.5.7 for B Train Standby Gas Charcoal Filter Media Efficiency (← links)
- 05000374/LER-2021-001, High Pressure Core Spray Inoperable Due to Water Leg Pump Breaker Cubicle Motor Contactor (← links)
- 05000445/LER-2020-001, Main Feedwater Pump Failure to Trip (← links)
- 05000483/LER-2020-001-01, Emergency Exhaust Inoperable Due to Fan Belt Degradation and Failure (← links)
- 05000317/LER-2020-001, Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a (← links)
- 05000298/LER-2020-004, Secondary Containment Differential Pressure Perturbation Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications (← links)
- 05000423/LER-2020-005, Loss of Safety Function - Secondary Containment (← links)
- 05000298/LER-2020-002, Secondary Containment Differential Pressure Perturbation Results in Potential Loss of Safety Function (← links)
- 05000458/LER-2020-004, Inadvertent Initiation and Injection of High Pressure Core Spray (HPCS) (← links)
- 05000331/LER-2020-001-01, Notice of Unusual Event and Unit Trip Due to Loss of Offsite Power Due to High Winds (← links)
- 05000220/LER-2020-001-01, Control Room Air Treatment System Inoperable (← links)
- 05000328/LER-2020-001, Ice Bed Inoperable Due to Exceeding Maximum Allowed Ice Bed Temperature (← links)
- 05000529/LER-2020-001-01, Reactor Trip on Low Steam Generator Level Signal (← links)
- 05000410/LER-2020-002-01, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000390/LER-2020-003, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000306/LER-1998-003-02, :on 980526,discovered Inadequate App R Fire Barriers & Unsealed Fire Barrier Penetrations.Caused by Lack of Adequate Separation of Safe Shutdown Equipment.Firewatch Has Been Established as Compensatory Measure (← links)
- 05000354/LER-1998-004-03, :on 980522,EDG B Declared Inoperable.Caused by Contamination W/Lubrication Oil in Delivered Fuel Oil. EDG Drained,Cleaned,Refilled & Sampled (← links)
- 05000423/LER-1998-031, :on 980519,incomplete Testing of P-4 Interlock Function Was Noted.Caused by Human Error & Inadequate Procedure Development.Revised Procedure, Ssps Refueling Tests (← links)
- 05000336/LER-1998-013-01, :on 980526,shutdown Cooling Sys Was Over Pressurized by Inadvertent Hpsip Start.Caused by Inadequate Evaluation in Original Plant Design.Appropriate Actions Were Taken to Ensure Sys Complies W/Design & Licensing Basis (← links)
- 05000220/LER-1998-012-01, :on 980521,determined That Fire Dampers Installed in Supply & Return Ducts to Auxiliary CR Would Fail Closed as Result of Loop.Caused by Inadequate Evaluation.Modified Affected Fire Dampers (← links)
- 05000423/LER-1997-054, :on 971029,noted That W Fuel May Exceed 10CFR50.46 Max Cladding Oxidation Design Criteria.Caused by Potentially non-conservative Modeling Criteria/Assumptions. Plant Specific Evaluation Has Been Performed by W (← links)
- 05000293/LER-1997-016, :on 971105,recirculation Sys Loop B Pump Trip Was Noted.Caused by Sp Inadequacy.Revised Procedure (← links)
- 05000271/LER-1998-014, :on 980521,inadequate Configuration in Control Methods Resulted in Plant Operation W/Degraded Vital Fire Barrier Subject to Plant TS Sr.Cause Could Not Be Determined.Replaced Seal (← links)
- 05000271/LER-1998-015, :on 980523,invalid ESF Actuation Including SBGTS Start,Containment Vent & Purge Isolation & Rbvi Was Noted.Caused by Failed Contactor Coil.Coil Was Replaced & Sys Was Returned to Normal (← links)
- 05000327/LER-1998-001-04, :on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation (← links)
- 05000336/LER-1998-011-01, :on 980519,determined That Valves Had Been Closing Completely Under No Flow Conditions.Caused by Improper Valve Setup & Failure to Verify Adequate Valve Closure.Valves Disassembled (← links)
- 05000368/LER-1998-002-04, :on 980520,EFAS Automatically Actuated to Maintain Water Level in a Sg.Caused by Inadequate self- Checking of Plant Response by Control Room Operations Personnel.Operations Personnel Counseled (← links)
- 05000368/LER-1998-003-01, :on 980520,determined That Surveillance of Control Element Assembly Position Was Not Being Performed for One Control Element Assembly Group,Per Ts.Caused by Inadequate Verification.Change Implemented (← links)
- 05000423/LER-1998-030, :on 980515,noted That Channel Calibr of Hydrogen Recombiners Did Not Meet Requirements of SR 4.6.4.2.b.Caused by Deficient Initial or Subsequent Reviews. Modified Hydrogen Recombiner Channel Calibr Procedures (← links)
- 05000302/LER-1997-042, :on 970730,inadequate Engineering Evaluation Resulted in Loss of Diverse RCS Leak Detection Capability. Caused by Personnel Error.Installed New RM-A6 Particulate Radioactivity Monitor (← links)
- 05000412/LER-1998-010-01, :on 980421,noted That non-safety Related Mechanical Seal Assembly Was Installed in Quench Spray Pump a 2QSS-P21A.Caused by Inadequate Knowledge & Training. Replacement Gland Seal Plates Were Procured (← links)
- 05000382/LER-1998-010, :on 980514,potential Overpressurization of N Sys Was Noted.Caused by Inadequate Design.N Sys Lineup Changed to Allow for Addl Overpressure Protection Through Alternate Existing ASME Section Viii Relief Valve (← links)
- 05000352/LER-1997-011, :on 971025,HPCI Sys Was Rendered Inoperable Due to Closing Turbine Exhaust Line Pciv.Caused by Valve failure.HV-055-1F072 Torque Switch Setting Was Increased within Analyzed Limits (← links)
- 05000352/LER-1997-011-01, Forwards LER 97-011-01,re Condition Prohibited by TS in That There Was Not Enough Assurance That Valve Would Continue to Meet TS Required Stroke Time When Restoring Valve to Operable Status.No New Commitments Made within Ltr (← links)
- 05000423/LER-1996-021, :on 960628,components Not Included in IST Program as Result of Programmatic Deficiencies,Was Discovered.Caused by Inadequate Mgt Commitment.Existing IST Documents & Procedures Will Be Reviewed & Revised (← links)
- 05000266/LER-1998-017, :on 980512,discovered Deficient Welds on B Loop Rrtd Piping Pipe Whip Restraint.Caused by Support Being Cut & Partially Removed During Plant Mod MR 84-284.Deficient Welds Were Repaired,Inspected & Confirmed to Perform (← links)
- 05000413/LER-1998-002-04, :on 980507,incorrectly Set Valve Leads to Elevated Condensate Storage Sys Temperature,Causing Condition Outside Design Basis of Plant,Was Noted.Caused by Inadequate Training.Alarm Response Guideline Revised (← links)
- 05000213/LER-1998-004, :on 980507,discovered Design Deficiency in Stack Radiation Monitor RMS-14B Isokinetic Sampling.Caused by Failure to Account for Spent Fuel Bldg Ventilation Flow. Will Develop CAP for RMS-14B (← links)
- 05000482/LER-1997-020, :on 971109,failure to Meet Snubber TS LCO Requirements Was Noted.Caused by Manufacturing Errors. Performed Sys Walkdowns,Replacement & Evaluations of Failed Snubbers & Associated Piping Sections (← links)
- 05000213/LER-1998-006, :on 980507,design Deficiency Was Found in Stack RM RMS-14B Sampling Lines.Caused by Design Not Meeting ANSI N13.1-1969 Stds.Corrective Action Plan for RMS-14B Is Being Developed (← links)
- 05000382/LER-1997-027, :on 971110,discovered Controller for Accws Valve Was Left in Manual.Caused by Personnel Error.Event Debriefing W/Control Room Staff (← links)
- 05000352/LER-1998-003, :on 980213,ESF Actuation Due to Incidental Contact W/Rv Instrument Rack Occurred.Caused by Personnel Error.Counseled Individual Involved & Training for Site Personnel (← links)
- 05000302/LER-1998-004, :on 980212,unanalyzed cross-connecting of 480 Volt Busses Was Noted.Caused by Inadequate Design Controls. Administrative Controls Will Remain in Place (← links)
- 05000440/LER-1998-001, :on 980506,instruction Rev Results in Inadequate Testing & Missed TS Sr.Caused by Human Error.On 980506,testing of PRM RM High Alarm Relay Contacts Was Performed (← links)
- 05000318/LER-1998-003-01, :on 980507,relays out-of-calibration Were Noted Due to Bumped Dial & Actions Not Taken.Caused by Improperly Installed Cover.Technicians Will Be Trained on Event & Protective Covers Will Be Clearly Marked (← links)
- 05000213/LER-1998-003, :on 980505,compensatory Sampling Frequency Exceeded Time Limit W/Sw Effluent RM Inoperable.Caused by Personnel Error.Individual Was Counseled & Technicians Were Reminded of Sampling within Required Frequency (← links)
- 05000423/LER-1997-063, :on 971231,inadequate Operator Response Time for Inadvertent SI Event Was Noted.Caused by Conflicting Program Requirements.Porvs & Associated Downstream Piping Have Been Qualified for Water Relief (← links)
- 05000455/LER-1989-003-06, :on 890304,undervoltage Condition Occurred When Line Bus Tie Breakers Opened Due to Fault in Line. Monitors Returned to Normal Operations After Voltage Transient Passed & Breakers Reclosed (← links)
- 05000219/LER-1989-008, :on 890303,prevention of Secondary Containment Isolation from Loss of Air Event Identified.Caused by Inadequate Surveillance Testing of Air Support Sys.Formal Surveillance Program Will Be Developed (← links)
- 05000443/LER-1998-004, :on 980504,shift Manager Left Area Defined as CR Area While Performing SRO in CR Area Function.Caused by Personnel error.On-duty ROs Noted Absence of Shift Manager, Shift Manager re-entered CR Area & Received Counseling (← links)
- 05000498/LER-1998-004, :on 980430,entry Into TS 3.0.3 for Inoperable Fuel Handling Bldg Exhaust Ventilation Sys Occurred.Caused by Inadequate Plant Design Which Does Not Support Motor Repairs in AOT W/O Shutting Down Plant.Performed Maint (← links)
- 05000295/LER-1989-004-05, :on 890308,all Rod Position Indicators Dropped to Reading of Approx 220 Steps Due to Line Voltage Regulator Failure.All Indicator Channels Declared Inoperable & Operators Prepared to Ramp Unit Down (← links)
- 05000313/LER-1998-002-03, :on 980505,automatic Actuation of CREVS Occurred Due to Higher than Normal Radiation at Detector When Filtration/Vacuum Assembly Was Moved in Adjacent Area. Revised Procedures to Add Noted Precautions (← links)
- 05000313/LER-1989-008, :on 890122,determined That When Bypass Valve GCH-29 Normally Open,Ability of Radiation Monitors to Perform Required Functions Not Ensured.Caused by Error in Design Change in Bypass Line & Valve (← links)
- 05000271/LER-1998-012, :on 980430,six Primary Containment Isolation Valves Were Declared Inoperable.Caused by Failure to Adequately Define Standards for Reducing Contact Forces Caused by Sharp Edges.Event Rept Initiated (← links)
- 05000304/LER-1989-009-06, :on 890903,vent Stack Sping Flow Monitor 2LP084 Failed,Rendering Auxiliary Bldg Stack Radiation Monitor Inoperable.Caused by Personnel Error.Required Surveillance Performed (← links)
- 05000456/LER-1989-008-09, :on 890905,Sargent & Lundy Engineers Evaluation Determined That W/Uncorrected Setpoints,Allowable Tech Spec Value Would Have Been Exceeded.Caused by Unclear Design Documents.Analysis of Setpoints Performed (← links)
- 05000374/LER-1989-013-03, :on 890907,group I Isolation Was Received During Performance of Instrument Surveillance LIS-MS-401. Caused by Failure of Procedure to Provide Steps for Resetting Isolation Signal.Signal Reset (← links)
- 05000373/LER-1989-023-01, :on 890908,reactor Recirculation Process Sample Inboard Isolation Stop Valve Spuriously Went Closed W/No Apparent Isolation Signal Present.Caused by Short in Coil of Relay 1B21H-K72.Work Request Written (← links)
- 05000336/LER-1989-004, :on 890320,visual Insp of Mechanical Plug Revealed Circumferential Cracking at Top of Plug.Caused by Primary Water Stress Corrosion Cracking.Tube Replugged W/New Mechanical Tube Plug (← links)
- 05000368/LER-1989-016-01, :on 890903 & 18,continuous Fire Watch to Monitor Nonfunctional Fire Barriers Removed Due to High Airborne Activity.Caused by Failure to Establish Contingencies.Tech Spec Change Issued (← links)
- 05000213/LER-1989-014, :on 890904,svc Water Pumps a & B Flow Determined Less than Design Basis for Modes 1,2,3 & 4 During Inservice Insp Test.Caused by Failure to Predict Pump Performance.Performance Restored (← links)
- 05000313/LER-1988-025, :on 880307,reevaluation of Discrepancy Between Assumed Sys Flow Rates & Actual Rates During Reactor Bldg Purges Identified Twelve Releases from 1977-80 Which Exceeded Tech Spec Limits (← links)
- 05000313/LER-1988-022, :on 881216,identified Discrepancy Which Resulted in Potential Impact on Environ Qualification of Plant.Caused by Failure to Properly Evaluate Changes in Svc Water Flow to DHR Coolers.Plan Developed (← links)
- 05000368/LER-1989-004, :on 890301,discovered Plant Startup Procedure Inadequate Resulting in Inability to Automatically Transfer HPSI Pump Suction Prohibited by Tech Specs.Caused by Inadequate Procedure.Procedures Revised (← links)
- 05000298/LER-1996-009, :on 960725,App R Safe Shutdown Analysis Vulnerabilities Were Noted.Caused by Human Error.Performed Procedural Changes & Circuit Mods Were Made (← links)
- 05000456/LER-1989-004-04, :on 890306,auxiliary Feedwater Pumps Started Automatically Following Closure of Governor Valves.Caused by Defective Test Switch.Stable Plant Conditions Established. Temporary Procedure Changes Initiated (← links)
- 05000271/LER-1989-022, :on 890831,identified That Outboard Isolation Valve V70-117 Fed from Nonemergency Power Bus.Exact Root Cause Unknown But Design Spec Misinterpretation Suspected. Temporary Mod Implemented (← links)
- 05000333/LER-1998-004, :on 980501,initiated Manual Reactor Scram Due to Multiple Control Rod Drift Indications in Cr.Implemented Preventive Maint Evaluation for Control Rods & Similar Power Supplies to Determine Appropriate Preventive Maint Tasks (← links)
- 05000254/LER-1989-001-03, :on 890106,RCIC Pump Discharge Inboard Isolation Valve Failed to Open from Full Closed Position. Caused by Binding of Torque Switch on Valve Operator.Switch Replaced.Reportability Per Part 21 Possible (← links)
- 05000254/LER-1989-002, :on 890109,total of Combined Local Leak Rate Test Interval on MSIV Exceeded Specified Surveillance Interval of 18 Months.Caused by Misinterpretation of Tech Specs.Tech Specs Revised (← links)
- 05000354/LER-1989-017-01, :on 890830,reactor Scram Occurred Due to Result of Low Reactor Pressure Vessel Water Level Signal.Caused by Installation of Air Line Failure During Plant Const.Leak Check of All Soldered Connections Done (← links)
- 05000271/LER-1989-015, :on 890310,lo Lo Reactor Water Level Signal from ECCS B Resulted in Initiation Signals to HPCI & Rcic,Trip of RHR B Svc Water Pump,Trip of Uninterruptible Power Supply a & Startup of Diesel Generator B (← links)
- 05000456/LER-1989-009-05, :on 890902,failure of Main Steamline Safety Valve to Reseat Occurred.Caused by Preservice Error in Design of Valve.Vendor Recommended Upgrade Will Be Installed on Valve 1MSO17C.Remaining Valves Checked (← links)
- 05000336/LER-1998-009-01, :on 980501,LBLOCA Analysis Indicates Peak Clad Temp Could Exceed 2200 Degrees F.Caused by Failure to Identify Excessive Variability.Reanalyzed LBLOCA Using Current & Corrected Evaluation Models (← links)
- 05000313/LER-1989-002-01, :on 890120,reactor Trip Occurred Due to Failure in Main Generator Exciter & Two Reactor Coolant Pumps Tripped on Undervoltage When Bus H1 Failed to Fast Transfer to Offsite Power.Caused by Arcing in Exciter (← links)
- 05000271/LER-1989-012, :on 890303,west Switchgear Room CO2 Suppression Sys Initiated Triggering Control Room Toxic Gas Monitoring Sys.Caused by Latches in 1 H Fire Barrier Doors Not Being Periodically Inspected for Proper Operation (← links)
- 05000373/LER-1989-011, :on 890302,sys Auxiliary Transformer Tripped. on 890304,diesel Generator 2B Fuel Filter Inlet Pressure Gauge Found Leaking Fuel Oil Into Room.Caused by Damaged Gauge Due to Vibration.Line Plugged (← links)
- 05000336/LER-1986-007-01, :on 860901,during Monthly Control Room Surveillance Check,Steam Generator 1 Level Indication on Remote Shutdown Panel Indicated Zero Percent.Caused by Failure of Amplifier Assembly (← links)
- 05000245/LER-1989-018-01, :on 890822,site NRC Inspector Discovered That Two Restraining Metal Straps on CRD Sys Hydraulic Control Units Found Missing.Caused by Personnel Error Due to Missing Site Specific Analysis.Straps Reinstalled (← links)
- 05000271/LER-1998-010, :on 980428,determined That Installation of Wetwell Hardened Vent Sys Challenged Containment Systems in Event of Postulated Loca.Caused by Human Error.Closed Safety Class MOV in Vent Line as Interim Action (← links)
- 05000482/LER-1989-018, :on 890828,inoperability of Both Exhaust Sys Resulted Due to Failure to Place Dampers in Safeguard Position.Lesson Plan Issued on Tagging of Ventilation Dampers to Personnel (← links)
- 05000336/LER-1998-008-01, :on 980423,TS Violations Were Noted.Caused by Failure to Achieve Compliance to TS Requirements.Revised Appropriate Surveillance Procedures (← links)
- 05000454/LER-1989-008-08, :on 890830,determined That Auxiliary Feedwater Pump Suction Pressure Switch Setpoints Not within Allowable Values.Root Cause Under Evaluation.Switch Setpoints Set to Conservatively High Values (← links)
- 05000458/LER-1998-002-02, :on 980425,each of Two Trains of Annulus Mixing Sys Failed to Start During Testing Due to Different, Apparently Independent Causes.Eoi Personnel Performing Root Cause Analyses.Breaker Replaced (← links)
- 05000395/LER-1989-013, :on 890808,design Deficiency in Svc Water Pump House Ventilation Sys Confirmed.Deficiency Could Cause Flooding & Result in Failure of safety-related Electrical Power Supplies.Incident Reportable Per Part 21 (← links)
- 05000282/LER-1998-007, :on 980519,DG Logic Testing Was Performed. Caused by Four Lines of Reasoning Applied to Issue at Various Times in Past.Reviewed Control Circuits of EDGs & Control Circuits (← links)
- 05000368/LER-1986-018, :on 860720,discovered Blowdown Pipe Missing Required Pipe Whip Restraint.Caused by Inadequate Control of Deviations from Design Requirements During Original Const. Pipe Whip Restraint Installed (← links)
- 05000334/LER-1998-021, :on 980324,discovered Gas Voids in Low Head Safety Injection Discharge Piping to Suction Piping of Charging/Head Safety Injection Pumps.Cause of Event Not Established.Procedures Will Be Revised (← links)
- 05000313/LER-1989-007-01, :on 890318,determined That Postulated Break in HPI Line Upstream of Hpi/Rcs Cold Leg Connection Could Constitute LOCA Not Enveloped by Plant Design Basis.Caused by Inadequate Design Change Process (← links)
- 05000313/LER-1989-031, :on 890829,unexpected Control Room Isolation & Actuation of Control Room Emergency Ventilation Sys Occurred.Cause Undetermined.Further Investigation Into Cause Will Be Conducted (← links)
- 05000285/LER-1998-004, :on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised (← links)
- 05000293/LER-1985-008, :on 850331,while Performing Routine HPCI Operability Flow Test,Hpci Turbine Tripped on Overspeed. Caused by Faulty Connector in Turbine Control Sys.Connector & Rupture Disc Replaced (← links)
- 05000295/LER-1989-013-02, :on 890823,testing of Main Steam Safety Valves Revealed Majority of Valves Had Setpoints Low Outside +/- 1% Tolerance.Caused by Elevated Temps at Work Site.Plant Shut Down on 890826 & Instrumentation Evaluated (← links)
- 05000271/LER-1989-008, :on 890307,primary Containment Isolation Sys Group Three Isolation Occurred.Caused by Personnel Error. Personnel Involved Made Aware of Occurrence & Specific Details of Sys Logic (← links)
- 05000267/LER-1989-018, :on 890825,leak in Main Steam Ringheader of One of Loop I Steam Generator Modules Discovered & on 890827,37 Crack Indications Found in Inconel Ringheaders.Investigation in Progress.Plant Shut Down on 890829 (← links)
- 05000266/LER-1989-005, :on 890503,inoperability of Low Temp Overpressure Protection Sys Using Nitrogen Gas Discovered. Caused by Inadequate post-mod Testing.Nitrogen Regulators Moved to Location Near PORVs (← links)
- 05000368/LER-1988-023-01, :on 880219,inoperability of Mechanical Snubber on Main Steam Supply Piping Discovered.Caused by High Dynamic Loading of Piping & Snubber Due to Water Entrainment in Steam Piping.Snubber Replaced (← links)
- 05000313/LER-1988-027, :on 880422,containment Isolation Valve Inoperable.Caused by Lack of Documentation of Design Basis Info for Sys Piping Temp & Pressures in Original Plant Design.Design Change Package Developed (← links)
- 05000313/LER-1989-029, :on 890825,determined That Svc Water Sys Operating Procedure Allowed Operation of Sys in Configuration That Could Result in Sys Being Rendered Inoperable by Single Component Failure (← links)
- 05000369/LER-1989-021-01, :on 890623,discovered That Design of Sys Did Not Take Into Account temp-induced Difference in Pressure Gradients Inside & Outside Annulus.Caused by Design Deficiency.Sys Setpoint Mods Implemented (← links)
- 05000368/LER-1986-017, :on 860604,discovered That Required Type C Testing of Containment Isolation Valves Not Performed Resulting in Noncompliance W/Tech Specs.Caused by Personnel Error.Actions Taken to Test Affected Valves (← links)
- 05000313/LER-1989-004-01, :on 890120,high Pressure Injection Line Check Valve Failed to Reseat.Caused by Inadequate Design Change Process.Program of Visual Insp & NDEs Completed to Identify Any Sys Degradations Due to Thermal Stresses (← links)
- 05000373/LER-1989-015-01, :on 890428,fire Protection Valves Found to Exceed Surveillance Frequency Requirements of Tech Specs 4.7.5.1.1.a/b.Caused by Error in Two Station Procedures. Procedures Revised (← links)
- 05000368/LER-1989-003-01, :on 890216,personnel Determined That Valve Associated W/Train a Hydrogen Analyzer Exceeded Environ Qualification Parts Replacement Interval Since 1983.Caused by Personnel Error.Components Replaced (← links)
- 05000416/LER-1998-002-01, :on 980421,failure to Maintain Standby DG Seismically Qualified as Required by TS Was Noted.Caused by Failure to Comply W/Sys Operating Instruction 04-1-01-P75-1. Door Was Closed Immediately (← links)
- 05000306/LER-1998-002, :on 980201,defect in Primary Sys Pressure Boundary Was Observed on Motor Tube Base of Part Length CRDM Housing.Caused by Flaw on G9 Part Length Crdm.Unit 2 Part Length CRDMs Have Been Removed & Replaced (← links)
- 05000271/LER-1998-011, :on 980422,noted That HPCI & RCIC Systems Low Steam Supply Pressure Isolation Function Is Bypassed During Startup Contrary to Ts.Cause Under Investigation.Will Revise Procedures Re HPCI & RCIC Steam Supply Valves (← links)
- 05000271/LER-1996-025, :on 960924,determined That Primary Containment Nitrogen Purge Sys Inboard Torus Isolation Valve Leaked in Excess of TS Limits.Caused by Improperly Adjusted Mechanical Stop.Adjusted Mechanical Stop (← links)
- 05000368/LER-1989-008-01, :on 890506,overspeed Trip of Steam Turbine Driven Emergency Pump Occurred.Caused by Degraded Ramp Generator.Ramp Generator Replaced & Entire Speed Circuit Calibr (← links)
- 05000368/LER-1988-016, :on 880920,Tech Specs Limit for Containment Spray Sys Train B Actuation Response Time Exceeded.Caused by Inadequate Procedures.Procedures for Routine Periodic Response Time Testing Revised for Discrepancy (← links)
- 05000313/LER-1989-027, :on 890821,DHR/LPI Train B Injection Valve Removed from Svc for Maint W/O Being Demonstrated.Caused by Personnel Error & Inoperable Emergency Diesel Generator. Operator Counseled & Memo Issued (← links)
- 05000336/LER-1998-007-02, :on 980408,reanalysis of Ms Line Break Indicated Possible Fuel Failures.Cause Is Under Investigation.Siemens Analysis Will Be Completed Prior to Entering Mode 4 from Current Outage (← links)
- 05000373/LER-1989-014-01, :on 890428,error in Reactor Bldg Ventilation Isolation Damper Indicating Light Circuit Logic Found.Caused by Inconsistency Between Drawings & Method of Timing Damper Closing.Damper Repaired & Circuitry Modified (← links)
- 05000313/LER-1989-030, :on 890824,fire Barrier Between Adjacent Emergency Diesel Generator Rooms Did Not Meet NFPA Code Re Protection Against Spread of Flammable Liquids.Caused by Fire Barrier Degradation.Barriers Modified (← links)
- 05000336/LER-1989-007, :on 890613,condensate Polishing Facility Radiation Monitor 2-CND-RE-245 Operated W/O Source Check. Caused by Personnel Error.No Corrective Action Taken as Check Added to Procedure Before Violation (← links)
- 05000374/LER-1988-014-01, :on 881017,Type B & Type C Total Containment Leakage Exceeded Tech Spec Limit of 0.6La in Hydrogen Recombined Gas Control Valve.Caused by Dirty Seats on Valve.Seats Cleaned & Lapped (← links)
- 05000374/LER-1989-012-03, :on 890829,reactor Protection Sys Bus B Transfer Isolated,Causing Loss of Power to Shutdown Cooling Outboard Isolation Logic.Caused by Relay 2B21h-K35B Being Depressed Off Ctr.Isolation Logic Reset (← links)
- 05000333/LER-1989-014, :on 890817,HPCI Pump Turbine Declared Inoperable Due to Water in Lubricating Oil.Caused by Leaking Steam Supply Isolation Valve.Turbine Oil Sump Drained & Refilled W/New Oil (← links)
- 05000424/LER-1998-004, :on 980420,ECCS Accumulators Were Unable to Mitigate Consequences of an Accident.Caused by Incorrect Application of Scaling Data Into Calibration Procedures. Revised Calibration Procedures (← links)
- 05000354/LER-1989-013-02, :on 890629,failure to Perform Required Local Leak Rate Testing on Hpci/Rcic Turbine Exhaust Vacuum Relief Piping Identified.Caused by Valves Not Being Included in Scope of Inservice Test Program (← links)
- 05000423/LER-1998-016, :on 980223,potential Air/Gas Intrusion in Chemical & Volume Control Sys Was Noted.Caused by Inadequate Initial Design.No Cause for Corrective Actions Because Both Flow Paths Were Operable (← links)
- 05000304/LER-1985-022-01, :on 851015,fuel Handling Accident Radiation Monitor Exceeded High Alarm Setpoint of 300 Mrem/H Due to High Exposure Rate from Upper Internals,Resulting in Closure of Containment Purge Valves.Procedure Revised.W/Undated Ltr (← links)
- 05000423/LER-1997-060, :on 971209,ineffective Implementation of PASS Program Was Noted.Caused by Failure of Mgt to Implement Effective PASS Program That Ensured Compliance W/Ts.Pass Has Been Incorporated Into Millstone Maint Rule as (a)(1) Sys (← links)
- 05000416/LER-1989-008, :on 890523,two Redundant Secondary Containment Isolation Valves Failed to Close within 4 Limit.Caused by Failure of Internal Disks of Exhaust Valves.Exhaust Valve of Actuator of Each Damper Replaced (← links)
- 05000304/LER-1989-008-07, :on 890624,breaker 27 Opened Causing Power Loss to NSSS Annunciators in Control Room.Caused by Binding of Breaker Mechanism Resulting in Insufficient Contact Pressure.Breaker 27 Removed & Replaced (← links)
- 05000206/LER-1989-018, :on 890527,voluntary Entry to Tech Specs 3.0.3 Done to Perform Surveillance of Containment Spray Sys Pump. Caused by Inadequate Tech Specs (Ts).Ts 3.3.1 Rev Planned to Preclude TS 3.0.3 Entries for Similar Events (← links)
- 05000245/LER-1989-013, :on 890502,core Spray Sys Orifice Flanges W/Incorrect ANSI B16.5 Rating Discovered.Orifice Plate Flanges Replaced & Core Spray Sys Returned to Svc (← links)
- 05000336/LER-1989-005-02, :on 890330,automatic Test Insertion (ATI) Module Connector Did Not Mate Smoothly W/Engineered Safeguard Actuation Sys Cabinet Socket Resulting in Safety Injection Actuation Signal Actuation (← links)
- 05000368/LER-1987-010, :on 870522,plant Protection Sys Panels Seismic Qualification Compromised Due to Loose Fasteners.Caused by Personnel Error When Personnel Elected Not to Tighten All Screws.Personnel Counseled (← links)
- 05000368/LER-1989-001-01, :on 890503,reactor Protective Sys Instrumentation Declared Inoperable Due to Channel Failing Low Intermittently.Caused by Misinterpretation of Procedure. Procedural Guidance Will Be Issued (← links)
- 05000368/LER-1984-018, :on 840618,Train B of Sodium Hydroxide Addition Sys Discovered Inoperable During Monthly Surveillance Test. Caused by Personnel Error.Administrative Procedure Revised to Provide Clarification (← links)
- 05000313/LER-1989-018, :on 890501,reactor Tripped & Inadvertently Jarred Turbine Control Panel Containing Mercoid Switches for Turbine Trip Functions.Caused by Caution Label Missing from Control Panel.Warning Placard Installed (← links)
- 05000368/LER-1986-016, :on 860617,pressurizer Low Pressure Trip Remained Bypassed at Pressure Greater than Allowed.Caused by Personnel Error Resulting in Inadequate Procedure.Plant Protection Sys Calibr Procedures Revised (← links)
- 05000373/LER-1989-016, :on 890502,Tech Specs Violated.Caused by Diesel Generator Surveillances Being Revised Incorrectly After Diesel Generator Prelube Mods Installed.On 890503,diesel Generator Would Not Shut Down (← links)
- 05000304/LER-1989-006-06, :on 890426,discovered That power-range Nuclear Instrument Channel Defeated on Power Mismatch Switch,Rod Stop Bypass Switch & Upper & Lower Current Comparator Switches.Caused by Personnel Error (← links)
- 05000313/LER-1989-026, :on 890627,four Tech Spec Fire Barriers Found Not Included in Fire Barrier Penetration Log & Omitted from Insp.Caused by Personnel Error.Fire Barrier Visual Insp Procedure & Penetration Log Revised (← links)
- 05000461/LER-1998-019, :on 980417,noted Failure to Satisfy TS for Ensuring That Electrical Loads Properly Sequence Onto safety-related Buses.Caused by Inadequate Surveillance Procedures.Will Revise Procedures 9080.21 & 9080.22 (← links)
- 05000213/LER-1989-008, :on 890425,discrepancy Discovered in Facility Design Basis Large Break LOCA Analysis.Caused by Use of non-LOCA Model Vol in LOCA Model Applications.Administrative Control to Reduce Tech Specs Limit Implemented (← links)
- 05000265/LER-1988-007, :on 880413,determined That Measured Combined Leakage Rate from Penetrations & Valves Exceeded Tech Specs Limit.Caused by Normal Wear.Repairs & Replacements Completed as Necessary (← links)
- 05000369/LER-1989-015-02, :on 890721,determined That Control Room Ventilation Sys Did Not Meet Required Tech Spec Positive Pressure of at Least +0.125-inches Water Gauge Relative to Outside Atmosphere.Caused by Design Oversight (← links)
- 05000245/LER-1988-005, :on 880527,insufficient Containment Interlock Setpoint to Ensure That ECCS Pump Caviation Would Not Occur. Caused by Single Failure That Exceeds Margin of Safety. ECCS Suction Strainers Replaced (← links)
- 05000295/LER-1989-009-04, :on 890620,equipment Attendant at Remote Shutdown Panel Inadvertently Started Auxiliary Feedwater Pump.Caused by Personnel Error.Pump Control Transferred to Main Control Board & Pump Secured (← links)
- 05000271/LER-1989-009, :on 890628,lack of Redundancy in RHR Svc Water Sys Discovered.Caused by Control Loop Functional Requirement Re Operation of Valve Not Properly Noted During Original Plant Design.Mod Made to Provide Power (← links)
- 05000304/LER-1989-007-02, :on 890428,discovered That Vent Stack Radiation Monitor Found in High Radiation Mode.Cause Unknown.Vent Stack Monitor Realigned to Normal Operation.Procedure Change Authorizes Performance of Surveillance (← links)
- 05000368/LER-1986-015, :on 860801,review of Fire Barrier Penetration Log Identified 55 Penetrations Not Inspected within Tech Spec Required Interval.Caused by Inadequate Procedure & Personnel Error.Log & Test Procedures Revised (← links)
- 05000313/LER-1988-030, :on 890620,determined That Unacceptable Modeling Technique Used in Stress Calculations,Potentially Affecting Seismic Capabilities of Eccs.Mods of Affecting Piping Completed (← links)
- 05000313/LER-1988-020-01, :on 881103,nonsafety-related Ventilation Sys Affected Penetration Room Ventilation Sys Capability to Process Penetration Leakage Following Design Basis Accident. Caused by Failure to Assess Sys Impact (← links)
- 05000263/LER-1998-002-02, :on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed (← links)
- 05000309/LER-1988-005, :on 880523,potential Harsh Environ Postulated for Unqualified Solenoid Valves.Emergency Operating Procedures Revised to Manually Isolate Vent Lines Following Safety Injection Actuation Signal (← links)
- 05000423/LER-1989-015-01, :on 890622,plant line-up Was Not Per Tech Spec 3.8.3.2 & on 890620,emergency Diesel Generator B Was Removed from Svc Due to Failed Surveillance Test.Caused by Personnel Error.Operating Procedures Revised (← links)
- 05000368/LER-1987-002, :on 870213,discovered Degraded Fire Barriers Due to Installation of Improper Seal Matl in Seismic Gap Separating Adjacent Bldgs.Caused by Inadequate Instructions During Const Phase.Fire Watch Established (← links)
- 05000454/LER-1989-005-07, :on 890501,diesel Generator Failed to Load to 5,500 Kw within 60 Due to Deficient post-maint Testing. Caused by Max Fuel Setting on Fuel Control Sys Set Too Low. Fuel Control Sys Properly Adjusted (← links)
- 05000313/LER-1988-028, :on 880831,discovered That Piping Span Lengths Between Containment Bldg Penetrations & First Piping Supports Unacceptable.Caused by Inadequate Judgement of Original Designer.Piping Requalified (← links)
- 05000271/LER-1989-019, :on 890501,primary Containment Isolation Sys Group III & Standby Gas Treatment Sys Initiations Occurred. Caused by Reactor Bldg Ventilation Radiation Monitor Sensor Malfunction.Sensor/Converter Replaced (← links)
- 05000271/LER-1989-014, :on 890607,RCIC Sys Inoperable Due to Motor Burn Out on RCIC-21 Valve.Caused by Prior Overcurrent Condition & Repeated Cyclic Operations During Testing.Plant Procedures Revised Re Consecutive Operations (← links)
- 05000354/LER-1989-010-01, :on 890414,Tech Specs Requirement for Breaker Alignment Verification within One H of Declaring Emergency Diesel Generator Inoperability Missed.Caused by Supervisor Error.Incident Reviewed W/Personnel Involved (← links)
- 05000354/LER-1989-011-01, :on 890427,high Radiation Area Not Properly Reposted Following Maint Per Tech Specs.Caused by Personnel Error.Exposure Doses for All Personnel Involved Reviewed & Safety Tagging Procedure Revised (← links)
- 05000368/LER-1988-022-01, :on 881103,two Discrepancies Noted in DBA Assumptions Used in Evaluations to Demonstrate Environ Qualification of Equipment in Containment.Caused by Lack of Clearly Defined Basis of Accident Analysis (← links)
- 05000368/LER-1986-006, :on 860421,inadvertent Actuation of Reactor Protective Sys Occurred.Caused by Channel a Sys Departure from Nucleate Boiling Ratio & High Local Power Density Trip Functions Bypassed During Shutdown Operations (← links)
- 05000456/LER-1989-003-05, :on 890302,control Room Ventilation Actuations Due to Momentary Loss of Voltage to Radiation Monitors. Caused by Perturbation of 345 Kv Sys.Evaluation Performed on Area & Process Radiation Monitors (← links)
- 05000368/LER-1986-020, :on 860712,discovered That Time Delay Function Associated W/Feeder Circuit Breaker from ESF Bus to Svc Water Pump Inoperable.Caused by Not Removing Jumper Wire. Jumper Wire Removed & Drawings Revised (← links)
- 05000313/LER-1989-014, :on 890426 & 0504,control Room Emergency Ventilation Sys Automatically Actuated Nine Times as Result of Spiking of Radiation Monitor 2RE-8750-1.Detector Replaced & Bad Connection in Holder Repaired (← links)
- 05000313/LER-1989-016, :on 890414,noted That Firewater Deluge Valve for Emergency Diesel Generator Not Repaired Since Crack Fitting Identified in Oct 1988.On 890201,sys Inoperable While Attempting to Replace Fitting (← links)
- 05000313/LER-1989-013, :on 881025,anchor Support for Core Flood Tank (CFT) T2A Vent Line Not Seismically Qualified & Operability of CFT Could Not Be Assured.Caused by Missing Anchor Support.Anchor Support Modified (← links)
- 05000374/LER-1989-009-03, :on 890619,RCIC Steam Line Hi Flow Isolation Switch Found to Have Diaphragm Leak.Probably Caused by Torn Diaphragm.Failed Switch Sent to Vendor for Detailed Insp. New Switch Installed (← links)
- 05000368/LER-1989-010, :on 890425,discovered That Valve Stroke Surveillance Test for LPSI Sys & Refueling Water Tank Had Not Been Performed.Caused by Personnel Incorrectly Indicating Tests as Already Performed (← links)
- 05000368/LER-1986-014, :on 860627,emergency Diesel Generator Failed. Caused by Engine Fuel Starvation Due to Severely Fouled Y- Strainer 2F-195B Screen Element.Mesh Screen Internals of Y-strainers Removed (← links)
- 05000373/LER-1989-008, :on 890228,reactor Vessel Low Water Level 2 Switch Found W/Setpoint Out of Tolerance in Excess of Reject Limit During Surveillance.Caused by Setpoint Drift.Work Request L87899 Written to Replace Instrument (← links)
- 05000259/LER-1998-001-03, :on 980414,standby Gas Treatment Sys HEPA Filter Testing Was Not in Compliance W/Ansi Std Requirements.Caused by Lack of Understanding of DOP Testing. Filter Testing Training Will Be Provided (← links)
- 05000368/LER-1984-015, :on 840302,discrepancy in Fire Barrier Penetration 2099-0002,which Previously Evaluated Acceptable, Identified as Nonfunctional.Caused by Lack of Definitive Guidelines in Walkdown Program (← links)
- 05000368/LER-1989-007, :on 890424,snubber on Valve (2CV-4653) on Pressurizer Spray Line Found Disconnected While Performing Inservice Insp of Mechanical Snubbers.Caused by Inadequate Work Controls.Snubber on 2CV-4653 Replaced (← links)
- 05000271/LER-1989-016, :on 890330,automatic Start of Core Spray & Sys a RHR Pumps Occurred While Pressurizing Primary Containment.Caused by Inadequate Procedure.Design Change That Implemented Logic Change Reviewed (← links)
- 05000265/LER-1989-004-08, :on 890811,atmospheric Containment Atmosphere Dilution Sys Unable to Perform W/Loss of Unit 2 Diesel Generator.Caused by Design Error.Procedure Changes to Alert Operators of Design Deficiencies Implemented (← links)
- 05000271/LER-1989-020, :on 890811,procedure Controlling Battery Maint & Testing Discovered Not Consistent W/Tech Spec 4.10.2.a Requirements.Caused by Inadequate Tech Spec Review of Procedure Rev.Plant Procedure Revised (← links)
- 05000416/LER-1989-013, :on 890814,MSIV B21F022B Failed to Close Upon Demand from Automatic & Remote Manual Actuation Signals. Caused by Elastomer Seat Matl Extruding Into Exhaust Port Vent Hole.Dual Valves Replaced.Part 21 Related (← links)
- 05000313/LER-1989-012, :on 890402,discovered That High Energy Line Break Door Covered,Resulting in Condition Outside Design Basis of Main Feedwater Line Break in Piping Penetration Room.Caused by Personnel Error.Cover Removed (← links)
- 05000245/LER-1996-023-01, :on 960306,movement of New Fuel Assemblies Over Spent Fuel Pool Resulted in Condition Outside of Design Basis of Plant.Caused by Personnel Error.New Fuel Elevator Tagged Out & Deenergized to Prevent Use (← links)
- 05000271/LER-1998-001, :on 980124,discovered That Penetration Seal Did Not Conform to Tested Configuration for 3-h Rated Seal. Caused by Lack of Formal Fire Protection Program at Time of Seal Installation.Repaired non-conforming Seal (← links)
- 05000219/LER-1998-008, :on 980409,building Dp Was Found to Be Out of Design Requirements.Caused by Lack of Awareness.Operations Dept Tour Logs Were Revised to Require Orw Dp Readings to Be Taken Once Per Shift (← links)
- 05000382/LER-1998-009, :on 980415,inadvertent ESF Actuation Occurred. Caused by Inadequate Configuration Control.Restored Incorrectly Lifted Lead to Terminal Point & Made Maint Personnel Aware of Drawing Discrepancy (← links)
- 05000336/LER-1988-006, :on 880218,local Leak Rate Testing Determined Combined Bypass Leakage Exceeded Tech Spec 3.6.1.2.C Limit. Caused by Debris Being Lodged in Seat Area of Valve.Duplex Strainer Installed in Piping Sys (← links)
- 05000029/LER-1989-004, :on 890224,determined That Control Room Emergency Air Cleaning Sys Inoperable from Mar 1988 to Aug 1988.Caused by Personnel Error.Electrical Leads Properly Terminated & Personnel Admonished (← links)
- 05000304/LER-1989-051, :on 890624,power Lost to NSSS Annunciators in Control Room Due to Opening of Breaker 27.Caused by Binding of Breaker Mechanism Triggering Insufficient Contact Pressure.Breaker 27 Removed & Replaced (← links)
- 05000312/LER-1989-005, :on 890218,discovered That Six Essential Flow Transmitters in Auxiliary Feedwater Sys Had Plastic Plugs Installed in Spare Conduit Connection Opening.Plastic Plugs Replaced W/Metal Plugs (← links)
- 05000266/LER-1989-004, :on 890421,discovered Nonconservative Analysis of Transfer to Containment Sump Recirculation Mode.Caused by Inadequate Analysis of Interruption of ECCS Flow During Large Break LOCA Scenario.Night Order Issued (← links)
- 05000313/LER-1989-017, :on 890420,discovered That Dhr/Low Pressure Injection Cooler Discharge Isolation Valves Not Tested Quarterly.Caused by Inadequate Mod Review Process.Provisions Made to Test Valves Every 3 Months (← links)
- 05000285/LER-1989-010, :on 890419,discovered That Polyflow Tubing to Sample Point on Roof Disconnected on Channel B of Two Toxic Gas Monitors.Caused by Deficiencies in Station Mod Program. Sample Tubing Replaced & Flow Rate Retested (← links)
- 05000313/LER-1989-015, :on 861209,RCS Loop B Flow Transmitters Sensing Line Not Properly Supported.Cause Undetermined.Engineering Insp of Similar Components Conducted During 1R7 & Revealed No Other Discrepancies (← links)
- 05000346/LER-1998-002, :on 980410,plant Tripped Due to High Pressurizer Level as Result of Loss of Letdow Capability. Makeup & Purification Demineralizer 3 Was Isolated Following Trip & Tagged OOS (← links)
- 05000373/LER-1989-022, :on 890810,RCIC Received Div I & Div II Isolation on RCIC High Steam Line Flow.Caused by Spurious High Steam Flow Signal.Rcic Sys Piping Integrity Verified & Isolation Logic Reset (← links)
- 05000423/LER-1998-023, :on 980411,ESF Actuation Occurred at Millstone Unit 3.Caused by Failure of CR Operations Personnel to Diagnose S/G C Level Loss Resulting from Abnormal Sampling Blowdown Lineup.Operating Procedure Revised (← links)
- 05000346/LER-1997-015, :on 971210,EDG Tachometer Circuit Was Noted Outside 10CFR50 App R Design Basis.Caused by Less than Adequate Development & Review of Mod 84-0183.Established Hourly Fire Watch in Cable Spreading Room (← links)
- 05000346/LER-1997-008, :on 970318,inadequate Testing of safety-related Logic Occurred.Overall Root Cause Will Be Completed by 980930 & Results of Evaluation Will Be Reported in Suppl to LER (← links)
- 05000455/LER-1989-003-04, :on 890227,containment Ventilation Isolation Occurred Due to Radiator Monitor Failure of Checksource Test.Caused by Faulty Detector.Detector Replaced & Monitor Tested & Returned to Svc (← links)
- 05000368/LER-1989-006, :on 890418,high Pressure Turbine Extraction Ruptured Resulting in Reactor Trip on High RCS Pressure. Caused by Pipe Wall Thinning Due to erosion-corrosion. Defective Wiring Replaced & Sys Satisfactory (← links)
- 05000338/LER-1989-004-01, :on 890405,determined That One Steam Generator Tube of Initial Sample Group Was Defective During 1989 Refueling Outage.Caused by Primary Water Stress Corrosion Cracking.Tubes Susceptible to Failure Plugged (← links)
- 05000416/LER-1989-004, :on 890420 & 26,RHR Pump a Tripped While Operating in Shutdown Cooling Mode.First Event Caused by Replacement of Power Fuse in RCIC Trip Circuit.Second Event Caused by Arcing in RCIC Circuit (← links)
- 05000354/LER-1998-003-01, :on 980407,concurrent Inoperability of a & B CR Chillers Was Noted.Caused by Personnel Error. Performed IST Tests,Equipment Repairs,Training & Revised Procedures (← links)
- 05000304/LER-1998-002-05, :on 980408,failure to Maintain Sufficient Swps Operable Was Noted.Caused by Personnel Error.Disciplined Unit Supervisor for Failure to Meet Expectation to Ensure Proper Plant Configuration Prior to Proceeding W/Test (← links)
- 05000313/LER-1989-025, :on 890623-0702,control Room Emergency Ventilation Sys Unexpectedly Activated Four Times.Caused by Induced Electrical Noise from Operation of Relays in Alarm Circuitry.Temp Instrumentation Repaired (← links)
- 05000213/LER-1998-001, :on 980409,seismic Monitor Sp Was Not in Compliance W/Ts.Caused by Inadequate Engineering Review. Submitted Proposed License Amend to Correct Issue (← links)
- 05000336/LER-1998-007-01, :on 980408,noted That non-conservative Assumptions May Result in Violation of Fuel Centerline Temp Fuel Design Limit.Caused Indeterminate.Will Complete Siemens Analysis Prior to Entering Mode 4 from Current Outage (← links)
- 05000423/LER-1989-004, :on 890216,fire Detection Discovered Inoperable Approx for 10 H.Caused by Personnel Error.Fire Watch Established.All on-shift Personnel Briefed Re Importance of Prompt Evaluation & Response to Fire Alarms (← links)
- 05000423/LER-1989-005, :on 890217,inadvertent Safety Injection Occurred on Train B.Caused by Personnel Error.All Operators Counseled on Importance of Being Cognizant of Actions When Manipulating Equipment (← links)
- 05000445/LER-1997-004, :on 980408,issues Discovered During Review of GL 96-01 Associated W/Ts Surveillances.Caused by Inadequate Test Procedures.Revised Applicable Test Procedures to Include Testing When Alternate Power Is in Service (← links)
- 05000456/LER-1989-005-06, :on 890422,instrument Inverter 111 Tripped & Repair Not Completed within 24 H Per Tech Spec.Caused by Shorted Capacitor Due to Normal Wear.Instrument Bus Energized & Inverter Repaired (← links)
- 05000455/LER-1989-002-07, :on 890220,boron Dilution Protection Sys Blocked for Greater than 1 H During Cold Shutdown.Caused by Lack of Administrative Tracking Tools Available to Operator. Timers W/Alarm Capability Made Available (← links)
- 05000368/LER-1989-009-01, :on 890420,determined That Emergency Diesel Generator 18-month Test Procedure Did Not Verify Fuel Pump Transfer Capabilities.Caused by Personnel Error.Procedure to Be Revised (← links)
- 05000295/LER-1989-008-06, :on 890620,inadvertent Start of Auxiliary Feedwater Pump Occurred Due to Distraction in Room.Caused by Personnel Error & Reversal Start/Stop Labeling on Pump Switch.Labeling Corrected (← links)
- 05000293/LER-1989-025, :on 890805,HPCI Sys Declared Inoperable & 7-day Tech Spec Limiting Condition for Operation Entered.Caused by Failure of Gland Seal Condenser Blower Motor to Start.Blower Motor Brushes Replaced & Blower Tested (← links)
- 05000368/LER-1989-015-01, :on 890809,personnel Identified Discrepancy Re Single Failure Design Criterion of Containment Hydrogen Analyzers.Caused by Inadequate Design Review Process. Evaluations Being Conducted to Correct Design (← links)
- 05000254/LER-1989-004-07, :on 890417,reactor Manually Scrammed Due to Electromagnetic Relief Valve 1-203-3D Being Stuck Open. Caused by Steam Leakage Past Pilot Valve & Obstruction of Drain Orifice.Relief & Pilot Valves Replaced (← links)
- 05000213/LER-1989-007, :on 890421,53 Steam Generator Hot Leg Mechanical Tubes Plugs Identified as Susceptible to Circumferential Cracking.Caused by Primary Water Stress Corrosion Cracking in Fabricated Plugs (← links)
- 05000317/LER-1998-007, :on 980404,eight of Sixteen MSSVs on Unit 1 Lifted at Pressure Above Setpoint Required in Tech Specs During as-found Lift Test.Cause of Event Currently Under Investigation.Reset Failed Valves (← links)
- 05000456/LER-1989-007-08, :on 890810,containment Bldg Fuel Handling Incident Area Radiation Monitor Went Into Alert Alarm & Interlock Actuation Due to Loss of Pulses.Caused by Failed High Voltage Power Supply in Monitor (← links)
- 05000271/LER-1989-021, :on 890725,containment High Range Radiation Monitor B Declared Inoperable Due to Failure to Respond. Caused by Open Circuit on Detector Signal Cable in Primary Containment.Instrument Will Be Repaired (← links)
- 05000219/LER-1998-005, :on 980330,automatic Depressurization Sys Inoperable.Caused by Inadequate Design.Mods Performed to Install Addl Cables,Prior to Plant Start Up (← links)
- 05000298/LER-1989-010, :Diesel Generator Room Ambient Temp Control Inadequacies Identified During NRC Insp on 870511-0619. Caused by Error in Original Plant Design.Design Change 87-132 Provided Permanent Mod to Eliminate Deficiency (← links)
- 05000298/LER-1989-006, :Control Bldg HVAC Design Concerns Identified During NRC Insp on 870511-0619.Caused by Inadequate Design. Steps to Install Permanent Essential Equipment That Will Provide Acceptable Room Temps Being Pursued (← links)
- 05000298/LER-1989-005, :Ac Voltage Regulation Concerns Identified During NRC Insp on 870511-0619.Caused by Inadequate Design. Design Change 88-263 Will Install Annunciation on 69 Kv Line to Alert Operator If Line Voltage Cannot Support ECCS (← links)
- 05000457/LER-1989-001-09, :on 890223,loss of RHR 2B Loop Occurred as Result of Procedural Deficiency.Caused by Failure to Identify That Placing Ssps in Test Would Not Block auto- Closure of Pump Valves.Procedure Revised (← links)
- 05000456/LER-1989-001, :on 890206,reactor Trip Occurred Due to Spurious Loss of Output Voltage on Instrument Inverter 112. Cause of Momentary Loss of Inverter Under Investigation. Feedwater Isolation Signal Reset (← links)
- 05000254/LER-1989-010, :on 890629,reactor Scram Occurred Due to Turbine Stop Valve Closure.Caused by Loose Connection on Condenser Low Vacuum Pressure Switch Indicating Lamp 1-5600-PS-105B.Connection Tightened (← links)
- 05000267/LER-1988-012, :on 880816,NRC Notified That Ga Co Environ Qualification Temp Profiles in CONTEMPT-G Calculated Lower Peak Temps for Line Break Scenarios.New Temp Profiles Developed by Numerical Applications,Inc (← links)
- 05000271/LER-1998-008, :on 980402,discovered That Control Bldg Cable Vault West Wall Fire Penetration 78-T11542 Contained Less than Three Inches of Seal Matl.Cause of Event Under Investigation.Seal Repaired & Rept Written (← links)
- 05000327/LER-1989-018-01, :on 890619,discovered That Both Trains of Auxiliary Bldg Gas Treatment Sys (ABGTS) Automatic Actuation Could Have Been Rendered Inoperable.Caused by Removal of Radiation Monitor During Testing (← links)
- 05000336/LER-1998-006-01, :on 980327,reactor Bldg Closed Cooling Water Sys Outside Design Upon Loss of Svc Water Occurred.Caused by Inadequate Consideration of All Postulated Single Failure Events.Procedures Will Be Implemented (← links)
- 05000298/LER-1998-006, :on 980402,SRVs Were Found Outside TS Limiting Safety Sys Setting.Caused by Corrosion Bonding of Pilot Disc to Pilot Seat.Removed SRV from Svc & Tested Utilized Pilot Discs (← links)
- 05000354/LER-1989-009-03, :on 890419,overvoltage Condition Affecting Class 1E Channel C Battery Charger Resulted in Loss of ECCS Instrumentation When Inverter Tripped.Caused by Personnel Error.Personnel Counselled (← links)
- 05000275/LER-2015-001, Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld (← links)
- 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability (← links)
- Licensee Event Report (← links)
- 05000458/LER-2015-002, Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments (← links)
- 10 CFR 50.73(a)(2)(iv), System Actuation (← links)
- 05000458/LER-2015-001, Operations Prohibited by Technical Specifications Due to Deficient Local Leak Rate Test Procedures Containing Erroneous Valve Alignments (← links)
- 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications (← links)
- 05000458/LER-2015-003, Operations Prohibited by Technical Specifications and Loss of Safety Function Due to Inoperability of Division 2 Containment Penetration Leakage Control System (← links)
- 05000530/LER-2015-002, Condition Prohibited by Technical Specification 3.0.4 Due to an Inoperable Atmospheric Dump Valve (ADV) (← links)