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Issue date | Title | Topic | |
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05000454/LER-1985-102 | 4 August 1993 | LER 85-102-01:on 851231,determined That FW 1D Preheater Bypass Valve 1FW039D in Svc 18 Days W/O Proper Operational Testing.Caused by Procedural Deficiency.Byron Administrative Procedure Bap 330-1 Will Be revised.W/930806 Ltr | Stroke time |
05000454/LER-1995-001, Informs That SER Issued Using LER 95-001 & Will Not Be Deemed as Ler.Lers 95-007 & 95-009 Will Not Be Used for Docket 50-454.LERs 95-003 Will Not Be Used for Docket 50-455 | 5 February 1996 | Informs That SER Issued Using LER 95-001 & Will Not Be Deemed as Ler.Lers 95-007 & 95-009 Will Not Be Used for Docket 50-454.LERs 95-003 Will Not Be Used for Docket 50-455 | |
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 | 9 October 1998 | 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 | Safe Shutdown |
05000455/LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR | 6 February 1987 | Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR | |
05000455/LER-1991-001, Advises That LER 91-001-00 Will Not Be Used | 18 June 1991 | Advises That LER 91-001-00 Will Not Be Used | |
05000455/LER-1993-005, Advises That LER 93-005 Will Not Be Used | 27 October 1993 | Advises That LER 93-005 Will Not Be Used | |
L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation | 31 October 1990 | Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation | Overspeed trip Loss of condenser vacuum |
M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) | 28 April 1999 | Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) | Shutdown Margin |
M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function | 17 March 1999 | Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function | Shutdown Margin |
ML17223A745 | 26 January 1990 | Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N | |
ML18041A225 | 3 October 1990 | LER 90-006-00:on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure revised.W/901003 Ltr | |
ML19257A522 | 26 December 1979 | Deficiency Rept Re Drop Rod Analysis.Interim Changes Will Be Implemented Pending Westinghouse Topical Rept Containing plant-specific,long-term Solutions | |
ML19269B787 | 31 December 1977 | 1977 Annual Rept, w/1977 Financial Review & Sec Form 10-Q,Quarterly Rept for Quarter Ended 780930. | Incorporated by reference |
ML19275A261 | 28 September 1979 | Proposed Secondary Water Chemistry Monitoring Programs | Grab sample |
ML19289C915 | 5 January 1979 | Interim Deficiency Rept on Button Heads Splits of Tendons Used to pre-stress Concrete Containment.Ref 781130 Nonconformance Rept 78-19.Describes Planned Test Program. Final Report Will Be Submitted by 790415 | |
ML19296D886 | 29 February 1980 | Second Interim Deficiency Rept Re Failure of Two Field Anchorheads for Horizontal Tendons Used to post-tension Concrete Containment.Addl Tendons Detensioned to Minimize Asymmetric Loads on Containment Bldg | |
ML19302F758 | 23 April 1985 | Corrects Typo in Second Interim Deficiency Rept 84-03 Re Installation of Butt Splices in Electrical Connectors.Rept Should Have Indicated That 564 Splices Documented But Not Inspected | |
ML19309H951 | 15 May 1980 | Interim Deficiency Rept 3 Re post-tensioning Anchorhead Failure.Acceptance Criteria Being Developed by Inryco,Inc to Establish Acceptability of Replacement Anchorheads.Testing Completed by 800630,w/final Rept Submitted at That Time | |
ML19320A802 | 27 June 1980 | Interim Deficiency Rept Re Failure of post-tensioning Anchorheads.Generally Concurs W/Inryco 800530 Rept.All Category B Heat Treat Lots Will Be Tested.Replacement Anchorheads from Accepted Heat Treat Lots Will Be Installed | |
ML19327A706 | 30 September 1989 | Monthly Operating Repts for Sept 1989 for Byron Nuclear Power Station Units 1 & 2.W/891010 Ltr | |
ML19327B401 | 31 July 1989 | Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. | |
ML19327B902 | 3 November 1989 | LER 89-009-00:on 891005,conflicting Info Re Signals That Initiate Automatic Isolation of Steam Generator Blowdown Lines Found.Caused by Preservice Design Implementation Deficiency.Lines Isolated & Procedure changed.W/891103 Ltr | High Energy Line Break |
ML19330A614 | 23 July 1980 | Deficiency Rept Re Intermittent Contact Operation of W-2 Switch.Util Will Not Implement Interim Fix Unless No Permanent Solution Is Available Prior to Fuel Load.Util Will Monitor Westinghouse Recommendations | |
ML19351E584 | 2 December 1980 | Interim Deficiency Rept Initially Reported on 801106 Re Westinghouse Electro-Mechanical Div Mfg 3-inch Gate Valves, Model 3GM88 Failing to Close Under Preoperational Test Conditions.Westinghouse Developing Generic Solution | |
ML19354D468 | 1 November 1989 | LER 89-008-01:on 890830,one Auxiliary Feedwater Suction Pressure Transmitter Calibr Not Head Corrected & Bases of Original Setpoints Not Questioned.Caused by Inadequate Procedures & Setpoint calculations.W/891101 Ltr | |
ML20003B663 | 17 February 1981 | Final Deficiency Rept Re Inadequate Qa/Qc Procedures for Cable Installation,Initially Reported on 810116.Thirty-two Hatfield Electric Procedures Have Been Revised Re Installation of Class IE safety-related Cable | |
ML20003F182 | 10 April 1981 | Final Rept Re Resolution of W-2 Switch Intermittent Contact Operation,Initially Reported on 800623.Adequacy of Basic Switch Design Confirmed.Switch Mfg Process Revised,Adding Steps to Reduce Internal Contamination During Assembly | |
ML20005D797 | 30 November 1989 | Monthly Operating Repts for Nov 1989 for Byron Nuclear Power Station Units 1 & 2.W/891208 Ltr | |
ML20005E239 | 26 December 1989 | LER 89-003-01:on 890227,area Radiation Monitor 2RT-AR012 Failed Automatic Checksource Test,Actuating Containment Ventilation Isolation Alarm.Caused by Faulty Detector. Detector Replaced & Monitor Returned to svc.W/891221 Ltr | |
ML20005G421 | 28 February 1989 | Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. | Hydrostatic |
ML20005G809 | 31 December 1989 | Monthly Operating Repts for Dec 1989 for Byron Nuclear Power Station,Units 1 & 2.W/900111 Ltr | |
ML20006D740 | 5 February 1990 | LER 87-004-01:on 870225,inadvertent Safety Injection Occurred During Maint Troubleshooting.Caused by Cognitive Personnel Error by Control Sys Technician Involved. Disciplinary Action Taken & Counseling done.W/900124 Ltr | |
ML20006E116 | 9 February 1990 | LER 90-001-00:on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter replaced.W/900126 Ltr | |
ML20006F352 | 31 January 1990 | Monthly Performance Repts for Jan 1989 for Byron Nuclear Power Station,Units 1 & 2.W/900212 Ltr | |
ML20006F716 | 16 February 1990 | LER 90-001-00:on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs.W/900109 Ltr | Reactor Vessel Water Level Grace period |
ML20009G273 | 24 July 1981 | Interim Deficiency Rept Re Vol Control Tank Level Control Sys,Initially Reported 810618.Potential for Adverse Control & Protection Sys Interaction Will Be Reviewed & Revised Per Westinghouse Recommendation.Next Rept by 810924 | |
ML20010A612 | 24 July 1981 | Deficiency Rept Re Motor Operated Valves at Facilities, Initially Reported 810618.Recommendations for Mods Made by Westinghouse | |
ML20010F607 | 30 June 1981 | Overpressure Protection Rept for Bryon/Braidwood Nuclear Power Plant Units 1 & 2 as Required by ASME Boiler & Pressure Vessel Code,Section Iii,Article NB-7300. | |
ML20010J169 | 9 May 1973 | Seismic Soil-Structure Interaction Analysis of Nuclear Power Plants. | Safe Shutdown Earthquake Operating Basis Earthquake |
ML20011E247 | 31 October 1989 | Analysis of Capsule U from Comm Ed Byron Unit 2 Reactor Vessel Radiation Surveillance Program. | |
ML20012B549 | 31 December 1989 | Annual 10CFR50.59 Rept 1989. W/900227 Ltr | Safe Shutdown Boric Acid Loop seal Fire Protection Program Overspeed trip Water hammer |
ML20012C122 | 28 February 1990 | Monthly Operating Repts for Feb 1990 for Byron Nuclear Power Station,Units 1 & 2.W/900312 Ltr | |
ML20012E915 | 15 March 1990 | Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001 | |
ML20024A347 | 9 June 1983 | Interim Deficiency Rept 83-07 Re Reactor Coolant Pump 1A Bearing Failure.Initially Reported on 830503.Defective Pump Internals Returned to Westinghouse to Determine Cause of Failure.Damaged Internals Replaced.Final Rept in 90 Days | |
ML20024H204 | 22 May 1991 | LER 91-005-01:on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet formalized.W/910522 Ltr | Scaffolding |
ML20028E313 | 14 January 1983 | Final Deficiency Rept 82-08 Re Insp Records for Structural Steel Bolted Connections.Statistical Sampling Plan Revealed Only One of 125 Reinspected Connections Did Not Meet Insp Criteria.Further Sampling Not Required | |
ML20028E319 | 10 January 1983 | Interim Deficiency Rept 82-09 Re Mechanical Snubber Bracket Interference.Initially Reported on 821203.Design Drawings & Vendor Production Info Under Review to Identify Suspect Snubber Assemblies.Next Rept Expected by 830215 | |
ML20028E651 | 21 January 1983 | Final Deficiency Repts 82-10 & 11 Re Rigid Strut Pins Mfg by Elcen.Initially Reported on 821223.Test Results Indicate No Load Capacity Data Values Violated.If Such Pins Were Used,Design Margins Not Exceeded | |
ML20029A646 | 20 February 1991 | LER 90-007-01:on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures reviewed.W/910219 Ltr | |
ML20029A690 | 13 September 1990 | LER 90-011-01:on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor trip.W/910221 Ltr |