Pages that link to "NRC Form 366, Licensee Event Report"
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The following pages link to NRC Form 366, Licensee Event Report:
Displayed 4 items.
- Licensee Event Report (← links)
- NRC Form 366 (redirect page) (← links)
- ENS 49288 (← links)
- 10 CFR 73.8, Information Collection Requirements: Omb Approval (← links)
- 10 CFR 73.71, Reporting of Safeguards Events (← links)
- 10 CFR 50.8, Information Collection Requirements: Omb Approval (← links)
- 10 CFR 50.73, Licensee Event Report System (← links)
- NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73 (← links)
- 05000400/LER-2007-004 (← links)
- 05000361/LER-2008-003 (← links)
- 05000323/LER-2010-001 (← links)
- 05000482/LER-2006-001 (← links)
- 05000397/LER-2004-007 (← links)
- IR 05000335/2015002 (← links)
- ML17122A249 (← links)
- ML17129A603 (← links)
- ML16217A174 (← links)
- ML16217A168 (← links)
- ML16221A001 (← links)
- ML16221A002 (← links)
- Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components (← links)
- Regulatory Guide 5.62, Physical Security Event Notifications, Reports, and Records (← links)
- ML18004A064 (← links)
- ML17360A154 (← links)
- ML17252A460 (← links)
- ML17252A459 (← links)
- ML17053A698 (← links)
- ML15317A016 (← links)
- ML15303A004 (← links)
- ML14241A697 (← links)
- ML13234A360 (← links)
- ML13234A116 (← links)
- ML13165A322 (← links)
- ML12334A505 (← links)
- ML12334A501 (← links)
- ML12334A497 (← links)
- ML12334A483 (← links)
- ML12334A481 (← links)
- ML12215A319 (← links)
- ML11346A541 (← links)
- ML11346A536 (← links)
- ML11346A530 (← links)
- ML11346A514 (← links)
- ML11346A511 (← links)
- ML11216A139 (← links)
- ML110740225 (← links)
- NRC Generic Letter 1983-43 (← links)
- ML17265A703 (← links)
- ML17264A751 (← links)
- ML17325B635 (← links)
- ML17317B544 (← links)
- ML17317A666 (← links)
- ML18144A998 (← links)
- NRC-17-0040, (LER) SER 17-S01-00 for Fermi 2 Regarding Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility (← links)
- RA-16-107, LER 16-S01-00 for Oyster Creek Nuclear Generating Station Regarding Special Nuclear Material Discovered Outside of Material Access Area (← links)
- L-2016-152, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Te (← links)
- DCL-15-042, Supplemental Licensee Event Report 1-2014-004-01 for Diablo Canyon, Units 1 and 2 Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power (← links)
- DCL-15-041, Supplemental LER 2-13-004-01 for Diablo Canyon, Unit 2 Regarding Technical Specification 3.8.1 Not Met Due to Failed Wire Lug on Emergency Diesel Generator 2-3 (← links)
- RC-18-0049, LER 2018-001-01 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator (← links)
- NL-16-108, LER 15-001-01 for Indian Point 2 Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate for Conta (← links)
- NL-15-124, LER 15-001-00 for Indian Point 2, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate for Cont (← links)
- NG-16-0225, LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit (← links)
- NL-11-2445, LER 11-S01-00 for Joseph M. Farley, Unit 1 Regarding Loss of Power to Security Systems (← links)
- RA-09-008, State of New York (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000023, Exelon Nuclear (RA-09-008), Oyster Creek Nuclear Generating Station, Facility Operating License No. DPR-16, NRC Docket No, 50-219, Licensee Event Report 2008-001-00, (← links)
- ML18194A800 (← links)
- ML100351172 (← links)
- ML092740162 (← links)
- ML090640445 (← links)
- NRC-09-0004, LER 08-S02-00 for Fermi 2 Regarding Fitness for Duty (FFD) Drug Testing Results in Reinstated Access Authorization Being Revoked (← links)
- ML090430136 (← links)
- NL-08-1906, LER 08-S01-00, for Edwin I. Hatch, Failure to Report Arrest Results in Inappropriate Access to Protected and Vital Areas (← links)
- NRC-08-0062, LER 08-S01-00 for Fermi 2 Regarding Unescorted Access Revoked Upon Discovery of Adverse Information (← links)
- ML082070076 (← links)
- ML18012A837 (← links)
- ML18011A224 (← links)
- ML18108A304 (← links)
- ML18018B146 (← links)
- ML17312B080 (← links)
- ML17285A874 (← links)
- ML15030A015 (← links)
- ML14269A388 (← links)
- CP-201000074, Official Exhibit - NYS000026-00-BD01 - Luminant Power (CP-201000074), Log TXX10010), Licensee Event Report 445/10-001-00, Trip Due to Pressure Relay Actuation on Main Transformer 01, Comanche Peak Nuclear Power Plant Unit 1 (Mar. 3, 2 (← links)
- ML100830413 (← links)
- ML071710233 (← links)
- ML003739442 (← links)
- ML18038B940 (← links)
- ML071650362 (← links)
- ML071560451 (← links)
- NG-07-0355, LER 07-S01-00 for Duane Arnold Regarding Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area (← links)
- ML063530017 (← links)
- ML063460247 (← links)
- ML062640550 (← links)
- ML062140446 (← links)
- ML993630051 (← links)
- ML18086A653 (← links)
- ML18086A386 (← links)
- ML18085B168 (← links)
- ML18085A331 (← links)
- ML18068A347 (← links)
- ML18046A560 (← links)
- L-13-194, LER 13-S02-01 for Perry, Unit 1 Regarding Security Weapon Left Unattended (← links)
- L-13-143, LER 13-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Security Weapon Left Unattended (← links)
- L-13-119, LER 13-S01-00 for Perry Nuclear Power Plant, Unit 1, Regarding Local Power Range Monitors Delivered to the Incorrect Address (← links)
- L-12-114, LER 12-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Potential Vulnerability in a Safeguards Security System (← links)
- L-12-083, LER 12-S01-00, Latent Software Error Resulted in Improperly Authorized Visitor Access Into Protected Area (← links)
- ML18152B712 (← links)
- LIC-14-0115, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091A/B for Post Accident Monitoring (← links)
- LIC-14-0105, Special Report on Inoperability of Containment Accident Radiation Monitor RM-091B for Post Accident Monitoring (← links)
- NRC 2018-0019, Cover Letter Correction - Licensee Event Report 2017-001-00 (← links)
- NLS2008058, LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning (← links)
- NRC-2016-0016, 2016/08/04 E-mail Capture - R.Guzman to W.Craft Opportunity to Review and Comment on an NRC Information Collection (Docket NRC-2016-0016) (← links)
- LR-N17-0087, 2016 Annual Radioactive Effluent Release Report (← links)
- RA-19-0027, Relief Request (19-ON-002) Alternative to Extend Code Case N-770-2, Inspection Item B Examination Frequency (← links)
- CP-201401014, Safeguards Event 60-Day Report (← links)
- ML19140A097 (← links)
- IR 05000316/1978034 (← links)
- ML18219B543 (← links)
- ML18283B339 (← links)
- W3F1-2009-0047, Notification of Potential Part 21 Re NRC Special Inspection Reportability Position Papers, Waterford Steam Electric Station, Unit 3 (← links)
- ML19150A303 (← links)
- ML18347B145 (← links)
- ML13083A106 (← links)
- ML19165A148 (← links)
- ML19150A307 (← links)
- ML19150A306 (← links)
- ML18243A135 (← links)
- ML17317B467 (← links)
- RA-19-0384, LER 20190-001-00 for H.B. Robinson Steam Electric Plant, Unit 2, Turbine Trip/Reactor Trip Due to Main Generator Lockout (← links)
- ML19282A009 (← links)
- ML19281A549 (← links)
- ML19281A536 (← links)
- ML19281A512 (← links)
- ML18043A974 (← links)
- ML052780336 (← links)
- ML052150216 (← links)
- RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area (← links)
- ML051730412 (← links)
- ML051050350 (← links)
- ML051050342 (← links)
- RA-19-0341, Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period (← links)
- ML19350C741 (← links)
- ML19347B625 (← links)
- ML19347A965 (← links)
- ML19345H254 (← links)
- ML19345G260 (← links)
- ML19345B994 (← links)
- ML19345B800 (← links)
- ML19340C299 (← links)
- ML19338F129 (← links)
- ML19338E250 (← links)
- ML19331D393 (← links)
- ML20003F730 (← links)
- ML20003C697 (← links)
- ML20003A983 (← links)
- RA-20-0031, Revision to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period (← links)
- ML20029D890 (← links)
- ML20028G380 (← links)
- ML20028E812 (← links)
- ML20028E355 (← links)
- ML20028E297 (← links)
- ML19294A248 (← links)
- ML20049A408 (← links)
- ML20049A336 (← links)
- ML20045H018 (← links)
- ML082280723 (← links)
- ML043450377 (← links)
- NRC-04-0083, LER 04-S02-00, Fermi 2 Unescorted Access Revoked Upon Discovery of Adverse Information in Background Check (← links)
- NL-20-0230, Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) (← links)
- ML042940376 (← links)
- LIC-04-0105, LER 04-S01-00 for the Fort Calhoun Station Regarding Inadequate Security Compensatory Measures for a Security Zone (← links)
- 05000325/LER-1981-092, Updated LER 81-092/01T-2:on 811226,action Statement 3.3.2b Not Entered When B21-LT-N017D-1 Instrument Failed Upscale. Caused by Failure of Operations Personnel to Recognize & Perform Required Action (← links)
- 05000325/LER-1981-093, Updated LER 81-093/01T-2:on 811226,reactor Protection Sys Vessel Low Level Trip instrument,1-B21-LT-NO17D-1,was Indicating Upscale.Caused by Personnel Failure to Recognize & Perform Tech Specs.Personnel Counseled (← links)
- 05000325/LER-1982-038, Updated LER 82-038/03L-1:on 820419.Reactor Scrammed When Electrical Bus 1A-1 Dc de-energized.Caused by Operator Error in Opening 125-volt Dc Battery Charger Output Breaker for Battery 1A-1.Breaker Closed & Power Restored to Bus (← links)
- 05000285/LER-1982-002, Forwards LER 82-002/03L-1 (← links)
- LIC-04-0002, LER 03-S02-00 for Fort Calhoun, Unit 1 Regarding Lack of Proper Compensation for a Security Zone (← links)
- ML033500129 (← links)
- ML033350423 (← links)
- ML033240358 (← links)
- ML033030498 (← links)
- ML032671101 (← links)
- 05000325/LER-1982-024, Supplemental LER 82-024/03L-2:on 820214,during Periodic Test,Discovered That Open Position Indication for Drywell to Suppression Vacuum Breaker X18H Could Not Be Achieved.Caused by Failure of Vacuum Breaker to Fully Stroke Open (← links)
- ML032660507 (← links)
- ML032580439 (← links)
- 05000301/LER-1982-005, Updated LER 82-005/01T-1:on 820727,discovered 2 of 3 Level Instruments on C Boric Acid Storage Tank Powered from Common Source.Cause Not Determined Due to Poor Early Maint of Documents.Wiring Corrected (← links)
- 05000333/LER-1993-027, Reissues LER-93-027 Re Fire Protection Sys Functional Test Procedure Weaknesses Due to Incorrect Date on Block 7 of Form NRC 366.Rept Text Remains as Issued on 940120 (← links)
- 05000348/LER-1981-010, Updated LER 81-010/03X-1:on 810429 & 30,containment Atmosphere Radioactivity Monitoring Sys R-11 Declared Inoperable When Filter Paper Did Not Advance.Caused by Paper Spool Slipping on Shaft.Drive Shaft Adjusted (← links)
- NG-03-0373, LER 03-S01-00, Duane Arnold Unattended Safeguards Information Outside of the Protected Area Caused by Personnel Error (← links)
- ML031320445 (← links)
- ML031260429 (← links)
- ML031250080 (← links)
- ML030860512 (← links)
- ML052790615 (← links)
- ML052790460 (← links)
- NRC-03-0020, LER 03-S01-00, Fermi 2, Unescorted Access Granted Prior to Verification of Fitness for Duty Drug Testing Results (← links)
- 05000261/LER-1981-002, Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modifie (← links)
- BSEP 03-0023, LER 2002-02-00 from Brunswick, Unit 2 Regarding Remote Shutdown Panel Power Supply Inventer Design Deficiency (← links)
- ML030380531 (← links)
- ML20062L218 (← links)
- ML20062J428 (← links)
- ML042880434 (← links)
- 05000321/LER-1981-120, Updated LER 81-120/01T-1:on 811105,AE Advised That in Event of Main Steamline Break or Scram Discharge,Isolation of HPCI & Reactor Core Isolation Cooling Sys Could Occur.Caused by Erroneous Analysis.Event Would Not Occur (← links)
- ML023230339 (← links)
- BYRON 2002-0115, LER 02-S001-00 for Byron Station, Units 1 and 2, Unescorted Access Granted Based on Falsified Information Provided by an Individual (← links)
- LIC-02-0115, LER 02-S01-00 for Fort Calhoun Unit 1 Regarding Possible Error in Classification of Safeguards Material on September 6, 2002 (← links)
- ML20059E795 (← links)
- ML022250669 (← links)
- ML20058F907 (← links)
- 0CAN050202, LER 02-S01-00 for Arkansas Nuclear One Units 1 and 2, Compensatory Measures Were Removed While a Security Perimeter Intrusion Detection Microwave Field Remained Disarmed (← links)
- 05000318/LER-1983-007, Followup LER 83-007/01T-0:on 830203,de-energization of Reactor Protection Sys (RPS) Channels Caused PORV & Pressurizer Quench Tank Rupture Disk to Open.Caused by Blown Fuse in RPS Channel a Due to Crossed Leads in Inverter 21 (← links)
- ML021050340 (← links)
- 05000325/LER-1982-135, Supplemental LER 82-135/03L-1:on 821019,1.5-inch Discrepancy Noted Between Narrow & Wide Range Instruments.Caused by Inoperable RTGB Level Instruments.Plant Mod Package Developed to Increase Accuracy (← links)
- 05000325/LER-1982-127, Updated LER 82-127/01T-1:on 821103,quick Start Testing of Diesel Generators 2,3 & 4 Not Performed for 12 H Period Per Tech Spec.Caused by Failure to Enter Requirement Into Daily Surveillance Rept on 821102.Testing Performed (← links)
- ML020590441 (← links)
- ML020280075 (← links)
- 05000261/LER-1980-027, Updated LER 80-027/01T-1:on 801122,relay RT-9 in Reactor Protection Train a Failed to re-energize During Periodic Test of Reactor Protection Logic.Caused by Shorting of Lead Wire Connection to Coil Wires.Relay Replaced (← links)
- 05000366/LER-1980-096, Updated LER 80-096/03X-2:on 800619 & 27,w/reactor Mode Switch in Run,Reactor Bldg to Torus Vacuum Breaker Isolation Valve Failed to Open.Caused by Failure of D-P Switch to Actuate.Switch Replaced (← links)
- 05000261/LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised (← links)
- 05000416/LER-1982-180, Final LER 82-180/03L-0:on 821227,isolation Valve for Hose Station in Control Room Replaced Due to Leaking Which Pressurized Hose.Addl Hose Run to Supply Backup Fire Protection.Leaking Valve Replaced.Sys Returned to Svc (← links)
- 05000313/LER-1983-023, Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being Developed (← links)
- ML20080B524 (← links)
- 05000325/LER-1983-045, Updated LER 83-045/03L-2:on 830919 & 24,inboard PCIV Steam Supply Valve ES1-F007 to RCIC Sys Would Not Completely Reopen.Caused by Loose Limitorque Motor Operator Spring Pack (← links)
- 05000324/LER-1983-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking (← links)
- 05000313/LER-1983-007, Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure (← links)
- ML20073B530 (← links)
- 05000289/LER-1984-004, Forwards Corrected LER 84-004-00 Re Misplugged Steam Generator Tubes.Rept Date Corrected & Licensee Contact Changed (← links)
- RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period (← links)
- 05000325/LER-1982-108, Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced (← links)
- ML20113D290 (← links)
- 05000317/LER-1982-022, Updated LER 82-022/01T-1:on 820503,total Type B & C Penetration Leakage Calculations Compared to Wrong Spec. Caused by Incorrectly Revised Local Leak Rate Surveillance Test Procedure.Procedure Revised (← links)
- ML20137L786 (← links)
- IR 05000271/1985036 (← links)
- ML20137A840 (← links)
- ML20136D400 (← links)
- ML20136D376 (← links)
- ML20148T815 (← links)
- ML20148Q430 (← links)
- 05000289/LER-1997-006, Forwards LER 97-006-00,resulting from Violation of TS 3.3 & Declaring Reactor Bldg fans,AH-E-1B & C,Inoperable on 970424 (← links)
- IR 05000382/1997009 (← links)
- ML20147B701 (← links)
- ML20141L897 (← links)
- ML20138Q549 (← links)
- ML20133J077 (← links)
- ML20133J008 (← links)
- ML20133H945 (← links)
- ML20132C192 (← links)
- ML20132B797 (← links)
- ML20128B869 (← links)
- ML20128B681 (← links)
- ML20127C396 (← links)
- ML20126L869 (← links)
- ML20126L789 (← links)
- ML20126L516 (← links)
- ML20126L512 (← links)
- ML20126J621 (← links)
- 05000289/LER-1998-010, Forwards LER 98-010-00 Re Potential Violation of Design Criteria During Single Auxiliary Transformer Operation Reported on 980825.Second & Associated Issue Was Identified & Reported on 980916,as Suppl Info IAW 10CFR50.72(c) (← links)
- 05000289/LER-1998-008, Forwards LER 98-008-00,re Radiation Monitor RM-A8G-High Which Was Inoperable for More than 7 Days Due to Less than Adequate Performance of Calibr Surveillance (← links)
- ML20149E295 (← links)
- ML20196G582 (← links)
- ML20196G186 (← links)
- ML20196G163 (← links)
- ML20196G093 (← links)
- ML20195H168 (← links)
- ML20195B973 (← links)
- ML20199M068 (← links)
- ML20198P183 (← links)
- ML20198J974 (← links)
- ML20198G756 (← links)
- ML20198E638 (← links)
- ML20198D878 (← links)
- ML20206E658 (← links)
- ML20206E476 (← links)
- ML20205P229 (← links)
- ML20205D291 (← links)
- ML20204B672 (← links)
- ML20203K933 (← links)
- ML20203K858 (← links)
- ML20203K844 (← links)
- ML20203F494 (← links)
- ML20203F480 (← links)
- 05000302/LER-1997-040, Corrected Page 1 of LER 97-040-00,adding Rept Date in Block 7.On 971110,inadequate Engineering Documentation for safety- Related Large Bore Piping Analysis & Pipe Supports Noted. Caused by Personnel Error (← links)
- ML20196K588 (← links)
- ML20207G153 (← links)
- ML20207F349 (← links)
- ML20207C801 (← 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)
- ML20206P150 (← links)
- ML20206K181 (← links)
- ML20209E526 (← links)
- ML20209B445 (← links)
- ML20214Q220 (← links)
- ML20214Q177 (← links)
- ML20214Q153 (← links)
- ML20214H220 (← links)
- ML20212G130 (← links)
- ML20237H181 (← links)
- ML20237F622 (← links)
- 05000289/LER-1998-007, Forwards LER 98-007-00, Inoperable Intake Screen & Pump House Floor Drain Check Valves Due to Lack of Preventive Maint & Periodic Insps, Per 10CFR50.73.Rept Was Evaluated & Determined Reportable on 980720.W/o Encl (← links)
- ML20237B683 (← links)
- ML20237A120 (← links)
- 05000461/LER-1998-012, Forwards LER 98-012-00, High Differential Pressure Required to Close Excess Flow Check Valves Results in Valves Being Outside of Design Basis of Plant, IAW Requirements of 10CFR50.73 (← links)
- RA-19-0352, Duke Energy Carolinas, LLC - Relief Request for Alternative for Reactor Vessel Closure Stud Examinations (← links)
- 05000289/LER-1998-005, Forwards LER 98-005-00 Re Inoperable Fire Dampers Determined Reportable on 980416.No New Commitments Made within Ltr (← links)
- ML20247K519 (← links)
- ML20247G797 (← links)
- ML20245F724 (← links)
- ML20236X220 (← links)
- ML20236V666 (← links)
- 05000320/LER-1998-001, Forwards LER 98-001-00 Re Condition Which Was Evaluated & Determined to Be Reportable on 980615.NRC Form 366 Contains Abstract,Providing Brief Description of Evaluated Condition (← links)
- ML20236J791 (← links)
- ML20264E685 (← links)
- 05000285/LER-1989-002, Forwards Corrected LER 89-002 & LER 89-003 (← links)
- ML20235S739 (← links)
- ML20217P355 (← links)
- ML20217E773 (← links)
- ML20217C747 (← links)
- ML20216D350 (← links)
- ML20215E204 (← links)
- ML20215A011 (← links)
- ML20214V093 (← links)
- ML20214U738 (← links)
- ML20214U646 (← links)
- ML20214T100 (← links)
- ML20214S381 (← links)
- ML20214S302 (← links)
- ML20214S265 (← links)
- ML20214R955 (← links)
- ML20214R836 (← links)
- ML20211H742 (← links)
- ML20211H654 (← links)
- ML20211H623 (← links)
- 05000304/LER-1997-001, Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr (← links)
- ML21101A002 (← links)
- ML21116A174 (← links)
- RC-98-0133, Responds to Violations Noted in Insp Rept 50-395/98-04. Corrective Actions:Need for Adding Applicable Action Statement for Tt & Feedwater Isolation Automatic Actuation Logic as Part of Conversion to Improved TS Will Be Assessed (← links)
- L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With (← links)
- ML20246P564 (← links)
- ML20215C245 (← links)
- ML21196A485 (← links)
- ML21225A224 (← links)
- ML21244A281 (← links)
- ML20210L807 (← links)
- 05000456/LER-1986-009, Informs of Typo in LER 86-009-00 Re Issuance of Suppl to Ler.No Suppl Will Be Issued (← links)
- BSEP-99-0050, Informs NRC That Certain Category C,D & E Piping Welds in Units 1 & 2 Have Not Been Inspected in Accordance with Frequencies Provided by NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, (← links)
- 3F1297-34, Forwards LERs 97-039-00 & 97-040-00 Re Administrative Oversight,Submitted to NRC Without Rept Dates Being Added to Page 1 of NRC Form 366 (← links)
- 3F0397-01, LER 97-S01-00:on 970130,maint Activities in Circulating Water Sys Resulted in Protected Area Breach.Caused by Failure to Identify Security Function of Plant.Armed Security Was Established (← links)
- 05000368/LER-1985-022, Corrects Forwarding LER 85-022-00.Unit,docket & License Number Incorrectly Listed on Cover Ltr 2CAN118503 (← links)
- VR-SECY-18-0058, SRM-M220127A: Enclosure - Affirmation Session - SECY-18-0058 - Final Rule: Enhanced Weapons, Firearms Background Checks, and Security Event Notifications (← links)
- ML22026A376 (← links)
- ST-HL-AE-5721, LER 97-S02-00:on 970721,all Power Lost to Security Sys at Completion of Lighting DG Performance Test.Caused by Security Personnel Did Not Recognize Nature or Significance of Bypass Trouble Alarm.Training Conducted (← links)
- NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With (← links)
- NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With (← links)
- NPL-97-0565, LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 8 (← links)
- ML22154A296 (← links)
- ST-HL-AE-5481, Forwards Response to GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks, Per 10CFR50.54(f) (← links)
- 1CAN099401, LER 94-V01-00:on 940804,functional Test Procedure for Hydrogen Analyzer Was Not Adequate to Alert Plant Personnel.Caused by Personnel Oversight.Functional Test Procedure Has Been Revised (← links)
- 10 CFR 50.69(g) (← links)
- ML22298A228 (← links)
- ML22269A460 (← links)
- ML22269A459 (← links)
- ML22269A458 (← links)
- ML22269A457 (← links)
- ML22250A443 (← links)
- ML23107A140 (← links)
- ML23129A331 (← links)
- ML23128A338 (← links)
- ML23122A199 (← links)
- ML23115A481 (← links)
- ML23115A478 (← links)
- ML23115A477 (← links)
- ML20062H320 (← links)
- IR 05000219/1982017 (← links)
- SECY-18-0058, Response to SRM-SECY-18-0058 - Final Rule: Federal Register Notice for Enhanced Weapons, Firearms Background Checks, and Security Event Notifications (← links)
- ML23156A414 (← links)
- ML23152A135 (← links)
- ML23151A707 (← links)
- ML23151A525 (← links)
- ML23061A016 (← links)
- Regulatory Guide 5.83 (← links)
- ML23125A074 (← links)
- ML23251A016 (← links)
- ML23198A191 (← links)
- ML23326A048 (← links)
- ML24157A065 (← links)
- ML24008A105 (← links)
- ML24130A271 (← 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)
- ML24220A036 (← links)
- ML24220A035 (← links)
- ML24220A034 (← links)
- ML24220A033 (← links)
- 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal (← links)
- ML24208A038 (← links)
- 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 (← links)
- 05000339/LER-2023-001, Reactor Coolant Pressure Boundary Leak Due to Poor Weld Workmanship (← links)
- NL-23-0915, Manual Reactor Trip Due to Loss of Feedwater (← links)
- 05000528/LER-2023-002, Reactor Coolant System Degraded Pressure Boundary (← links)
- ML23299A176 (← links)
- 05000445/LER-2023-001-01, (Cpnpp), Automatic Reactor Trip Due to Lo-Lo Steam Generator Level (← links)
- 05000341/LER-2023-002, Technical Specification Completion Time Exceeded Due to Repairs on the MDCT Fan D (← links)
- 05000333/LER-2023-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation (← links)
- 05000333/LER-2023-003, Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem (← links)
- 05000374/LER-2022-003-02, Manual Scram Due to Lsophase Bus Duct Fire Followed by 2A RPS Normal Power Supply Trip (← links)
- 05000250/LER-2023-001, RCS Pressure Boundary Degraded (← links)
- 05000333/LER-2023-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation (← links)
- 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer (← links)
- 05000458/LER-2023-001, Ultimate Heat Sink Inoperable Due to Boundary Valve Leakage (← links)
- 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System (← links)
- ML23032A445 (← links)
- 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation (← links)
- ML23030A576 (← links)
- ML23030A400 (← links)
- 05000333/LER-2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas (← links)
- 05000269/LER-2022-001, Ultrasonic Examination Indications Identifies Degraded Reactor Coolant System Pressure Boundary (← 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)
- 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)
- 05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation (← 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)
- 05000282/LER-2022-001, Fuel Assemblies Incorrectly Placed in Spent Fuel Pool (← links)
- 05000373/LER-2022-003-01, Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000373/LER-2022-003, Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Multiple Component Failures (← links)
- 05000287/LER-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve (← 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)
- 05000270/LER-2022-003, Manual Reactor Trip Due to Main Feedwater Control Valve Positioner Malfunction (← links)
- 05000270/LER-2022-002, Regarding Automatic Actuation of Emergency Feedwater System Due to Main Feedwater Pump 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-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers (← links)
- 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- ML22063A703 (← 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)
- 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)
- 05000270/LER-2021-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 2 Main Feeder Buses (← links)
- 05000219/LER-2022-001, Compensatory Measures Not Implemented Per Sites Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure (← links)
- 05000333/LER-2021-003, Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure (← links)
- 05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure (← links)
- PLA-7977, Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications (← links)
- PLA-7976, Automatic Reactor Scram Due to Main Turbine Trip (← links)
- 05000397/LER-2021-002, Integrated Leak Rate Test (← links)
- 05000387/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by a C Isophase Bus Ground Fault (← 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)
- 05000333/LER-2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas (← links)
- 05000397/LER-2021-001, Breach of Secondary Containment (← links)
- 05000387/LER-2021-003, Automatic Reactor Scram Due to Main Turbine Trip (← 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)
- 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications (← links)
- ML24318C508 (← 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)
- 05000458/LER-2021-004, Core Monitoring System Software Modeling Error Resulted in Conditions Prohibited by Technical Specifications (← links)
- 05000440/LER-2021-002, Re Core Monitoring System Software Modeling Error Results in Conditions Prohibited by Technical Specifications (← links)
- 05000327/LER-2021-001, Sequoya Nuclear Plant, Unit 1, Reactor Trip on High Neutron Flux Rate Due to Dropped Control Rods (← links)
- 05000338/LER-2021-001, Manual Reactor Trip on Degrading Condenser Vacuum Due to Piping Failure (← 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)
- ML21162A109 (← links)
- NMP1L3400, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 13 (← links)
- 05000416/LER-2021-001, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate (← links)
- 05000483/LER-2021-001, Manual Actuation of Essential Service Water System (← links)
- 05000416/LER-2020-006-01, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000389/LER-2021-001, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center (← links)
- 05000416/LER-2020-005-01, Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000416/LER-2019-006-01, Failure to Meet Technical Specification 5.5.7 for B Train Standby Gas Charcoal Filter Media Efficiency (← links)
- 05000483/LER-2020-002-01, Reactor Trip and AFW Actuation Following Spurious MFRV Closure (← links)
- 05000483/LER-2020-001-01, Emergency Exhaust Inoperable Due to Fan Belt Degradation and Failure (← links)
- 05000416/LER-2020-006, Re Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000416/LER-2020-005, Re Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000483/LER-2020-007, Re B Pressurizer PORV Inoperable Due to Nonconformance with EQ Requirements (← links)
- 05000316/LER-2020-004, Automatic Reactor Trip on Low-Low 24 Steam Generator Water Level (← links)
- 05000334/LER-2020-001, Intake Structure Interconnecting Flood Door Found Open Resulting in a Loss of Train Separation for the Reactor Plant River Water System (← links)
- 05000255/LER-2020-002, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (← links)
- 05000316/LER-2020-003, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve (← links)
- 05000298/LER-2020-002, Secondary Containment Differential Pressure Perturbation Results in Potential Loss of Safety Function (← links)
- 05000458/LER-2020-003, Weep Holes Discovered in G-Tunnel Wall Result in Inoperable Safety Related Equipment (← links)
- 05000416/LER-2020-004, Automatic Reactor Scram Due to Reactor Feed Pump Trip (← links)
- 05000331/LER-2020-001-01, Notice of Unusual Event and Unit Trip Due to Loss of Offsite Power Due to High Winds (← links)
- 05000416/LER-2020-003, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram (← links)
- 05000220/LER-2020-001-01, Control Room Air Treatment System Inoperable (← links)
- 05000323/LER-2020-002, Manual Reactor Trip Due to Increased Main Generator Hydrogen Usage (← links)
- 05000331/LER-2020-001, Notice of Unusual Event and Unit Trip Due to Loss of Offsite Power Due to High Winds (← links)
- 05000410/LER-2020-002-01, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000333/LER-1998-005, :on 980529,declared HPCI Inoperable Due to Observed Lower than Normal Output Signal on Flow Controller. Replaced Flow Controller & Declared HPCI Sys Operable on 980530 (← 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)
- 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)
- 05000298/LER-1998-007, :on 980526,missed Surveillance Testing of Main Turbine Stop Valve Closure,Was Discovered.Caused by Failure to Effectively Implement TS Amend.Main Turbine Stop Valve Closure Scram Function Verified Operable (← links)
- 05000336/LER-1998-012-01, :on 980521,nonconservative Assumptions in Facility Loss of Normal FW Analysis Was Noted.Caused by Incorrect Calculation of SG Inventory During Lonf Event. Reanalysis of FSAR Loss of Normal FW Analysis Was Completed (← 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)
- 05000285/LER-1998-007, :on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC (← links)
- 05000382/LER-1997-030, :on 971114,discovered TS 3.6.3 Noncompliance Due to Design Error Associates W/Cars & Civs.Caused by Inadequate Mod.Valve CAR-201B Declared Inoperable (← 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)
- 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)
- 05000277/LER-1998-003-01, :on 980513,failure to Meet TS for Main Control Room Emergency Ventilation,Was Identified.Caused by Failure to Follow GP-25 Procedure Guidance.Main Control Room Emergency Ventilation Relays Inspected for Loose Screws (← links)
- 05000277/LER-1997-010, :on 971229,failure of 2A Reactor Feedpump Turbine to Trip,Occurred.Caused by Main Control Room pushbutton.2A RFPT Trip Device Repaired,Reinstalled & Tested to Prove Operability (← links)
- 05000277/LER-1997-009, :on 971109,reactor Scram Occurred.Caused by Generator Lockout Condition & Subsequent Turbine Trip Failure of 2A Reactor Feedpump Turbine to Trip on Demand During Recovery Activities.Reset Appropriate Scram Logics (← links)
- Form NRC 366 (redirect page) (← links)
- 10 CFR 50.73(b) (← links)