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 Issue dateTitleTopic
05000454/LER-1985-1024 August 1993LER 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 LtrStroke 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 50-4555 February 1996Informs 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 a9 October 1998Corrected 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 aSafe Shutdown
05000455/LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR6 February 1987Errata 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 Used18 June 1991Advises That LER 91-001-00 Will Not Be Used
05000455/LER-1993-005, Advises That LER 93-005 Will Not Be Used27 October 1993Advises That LER 93-005 Will Not Be Used
L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation31 October 1990Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)28 April 1999Rev 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) Function17 March 1999Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) FunctionShutdown Margin
ML17223A74526 January 1990Part 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
ML18041A2253 October 1990LER 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
ML19257A52226 December 1979Deficiency Rept Re Drop Rod Analysis.Interim Changes Will Be Implemented Pending Westinghouse Topical Rept Containing plant-specific,long-term Solutions
ML19269B78731 December 19771977 Annual Rept, w/1977 Financial Review & Sec Form 10-Q,Quarterly Rept for Quarter Ended 780930.Incorporated by reference
ML19275A26128 September 1979Proposed Secondary Water Chemistry Monitoring ProgramsGrab sample
ML19289C9155 January 1979Interim 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
ML19296D88629 February 1980Second 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
ML19302F75823 April 1985Corrects 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
ML19309H95115 May 1980Interim 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
ML19320A80227 June 1980Interim 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
ML19327A70630 September 1989Monthly Operating Repts for Sept 1989 for Byron Nuclear Power Station Units 1 & 2.W/891010 Ltr
ML19327B40131 July 1989Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel.
ML19327B9023 November 1989LER 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
ML19330A61423 July 1980Deficiency 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
ML19351E5842 December 1980Interim 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
ML19354D4681 November 1989LER 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
ML20003B66317 February 1981Final 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
ML20003F18210 April 1981Final 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
ML20005D79730 November 1989Monthly Operating Repts for Nov 1989 for Byron Nuclear Power Station Units 1 & 2.W/891208 Ltr
ML20005E23926 December 1989LER 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
ML20005G42128 February 1989Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation.Hydrostatic
ML20005G80931 December 1989Monthly Operating Repts for Dec 1989 for Byron Nuclear Power Station,Units 1 & 2.W/900111 Ltr
ML20006D7405 February 1990LER 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
ML20006E1169 February 1990LER 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
ML20006F35231 January 1990Monthly Performance Repts for Jan 1989 for Byron Nuclear Power Station,Units 1 & 2.W/900212 Ltr
ML20006F71616 February 1990LER 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 LtrReactor Vessel Water Level
Grace period
ML20009G27324 July 1981Interim 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
ML20010A61224 July 1981Deficiency Rept Re Motor Operated Valves at Facilities, Initially Reported 810618.Recommendations for Mods Made by Westinghouse
ML20010F60730 June 1981Overpressure Protection Rept for Bryon/Braidwood Nuclear Power Plant Units 1 & 2 as Required by ASME Boiler & Pressure Vessel Code,Section Iii,Article NB-7300.
ML20010J1699 May 1973Seismic Soil-Structure Interaction Analysis of Nuclear Power Plants.Safe Shutdown Earthquake
Operating Basis Earthquake
ML20011E24731 October 1989Analysis of Capsule U from Comm Ed Byron Unit 2 Reactor Vessel Radiation Surveillance Program.
ML20012B54931 December 1989Annual 10CFR50.59 Rept 1989. W/900227 LtrSafe Shutdown
Boric Acid
Loop seal
Fire Protection Program
ML20012C12228 February 1990Monthly Operating Repts for Feb 1990 for Byron Nuclear Power Station,Units 1 & 2.W/900312 Ltr
ML20012E91515 March 1990Ro: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
ML20024A3479 June 1983Interim 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
ML20024H20422 May 1991LER 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 LtrScaffolding
ML20028E31314 January 1983Final 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
ML20028E31910 January 1983Interim 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
ML20028E65121 January 1983Final 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
ML20029A64620 February 1991LER 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
ML20029A69013 September 1990LER 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
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