Geoffrey Edwards# QUERY174f04e30250221115d5591f52ce14e9
Geoffrey Edwards# QUERYdefeff5fceb9be3506b7f895cd908278
Geoffrey Edwards# QUERY4cbea275a1595ae9696ffb8f3ecabb19
Geoffrey Edwards OR Geoffrey Edwards
Geoffrey Edwards# QUERY2d7a53f45f19dba26d7b0e9c8a5d4338
Geoffrey Edwards# QUERYe13fa2bd42f220c27a9a74240ac85a26
Geoffrey Edwards# QUERY420d8dc2941dc88ea8f0a9236366c037
Geoffrey Edwards
Geoffrey Edwards# QUERY1d45a119198747bb11f7fff459543e85
Geoffrey Edwards# QUERY20ddf4d68872a9f5b407549b2e08215a
NRC/RGN-III/DRS/PSB false
Geoffrey Edwards# QUERY4923e17f82301dbb06ab5f3e89fd09ab
NRC/RGN-III/DRS/PSB true
Geoffrey Edwards# QUERY4bdee22ff13ebb696e63ac2726a4033b
NRC Region 3
Geoffrey Edwards# QUERY52aac42d8d4bbae7336732958b69451c
05000277/LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601
05000277/LER-1997-007, Forwards LER 97-007-00 Which Documents Event That Occurred at Peach Bottom Atomic Power Station,Units 2 & 3 on 740705
05000277/LER-1997-008, Forwards LER 97-008-00,reporting Discovery of safety-related Logic Components That Were Not Tested Per TS Surveillance Requirements on 740705
05000277/LER-1997-006, Forwards LER-97-006-00,concerning Unplanned ESF Actuation During 4-kV Electrical Bus Relay Testing Activities on 970923
05000277/LER-1997-004, Forwards LER 97-004-00 Re non-compliance of MCR Emergency Ventilation Sys TS Which Occurred on 970710
05000277/LER-1997-005-02, :on 970808,discovered TS non-compliance Associated W/Rod Block Contact Testing.Caused by Rev in Oct 1989,attempted to Consolidate Testing of Rod Block Logic from Two Instrument Panels.Procedure Revised
05000277/LER-1997-010-02, :on 971229,2A RFPT Failed to Trip When RO Pushed CR 2A RFPT Trip push-button.Caused by Intermittent Failure Mechanism.Repaired,Reinstalled & Tested Operability of 2A RFPT
05000278/LER-1994-006-03, :on 941110,identified That Flow Input Signals to APRMs Reading Higher than Actual Core Flow Conditions. Caused by Change in Plant Operating Strategy.Aprms Adjusted
05000278/LER-1997-003-01, :on 970404,TS Noncompliance Due to Loss of 3C RFP High Water Level Trip,Occurred.Caused by Failure to Correlate Turbine/Reset Light Problem to Inoperability. Operating Shift Procedures Revised
05000277/LER-1996-009, :on 961001,declared High Pressure Coolant Injection (HPCI) Sys Inoperable Due to Bearing Misalignment. Realigned Bearing Housing,Performed ST-O-023-200-2 Satisfactorily & Declared HPCI Sys Operable
05000278/LER-1997-001, :on 970122,determined Plant Thermal Power Exceeded 100% Due to Out of Tolerance Test Equipment.Retired Test Apparatus from Future Use & Will Review and Revise Procedures for Feedwater Temp Instruments
05000277/LER-1997-002-03, :on 970326,TS Violation Identified as Result of Reactor Operation Slightly in Excess of Licensed Thermal Power.Ctp Calculation Program Was Modified to Compensate for Recirculation Pump Motor Power Factor
05000277/LER-1997-001-03, :on 970318,TS Violation Due to non-conservative Average Power Range Monitor Flow Bias Scram Setpoints for Single Loop Operation.Procedural Enhancements to Ensure That Single Loop Flow Conditions,Accommodated
05000278/LER-1997-002-02, :on 970309,manual Scram Occurred Due to Loss of Forced Reactor Core Circulation at Power as Result of 13kv Feeder Breaker Auxiliary Switch Failure.Auxiliary Switch Assembly Was Cleaned & Lubricated
05000277/LER-1996-011-01, :on 961030,main Steam Line Relief Valve Actuation Occurred Due to Inadvertent Movement of Control Switch.Reactor Operator Immediately Recognized Situation & Reclosed Valve.Event Discussed W/All Crews
05000277/LER-1996-009-02, :on 961001,HPCI Sys Declared Inoperable Due to Bearing Misalignment.Hpci Booster Pump Procedure Will Be Revised to Provide Appropriate Guidance for Bearing Alignment
05000277/LER-1996-005-01, :on 960508,determined Units 2 & 3 Operated in Condition Prohibited by TS 3.8.1.Caused by Result of Actuation of Load Tap Changer Surge Protection Circuitry. Alternate Source Replaced
05000277/LER-1996-004-01, :on 960417,HPCI Sys Declared Inoperable Due to Leak in Cooling Water Relief Valve.Caused by Igscc.Hpci Cooling Water Relief Valve Was Replaced.W/Undated Ltr
05000278/LER-1996-002-03, :on 960624,room Cooler Associated w/3C LPCI Pump Discovered Inoperable.Caused by Inadequate Post Maint Testing.Room Cooler Fan Motor Wiring Corrected.Provided Staff W/Info Re Breaker Configuration Control
05000277/LER-1996-007-01, :on 960604,ESFA Occurred Due to Loss of One off-site Electrical Source as Result of off-site Substation Activities.Reset Isolation Logics & Restored Affected Sys
05000278/LER-1996-001-03, :on 960529,HPCI Turbine Control Valve Failed to Open as Expected During Performance of Routine Test O-023A-450-3.Caused by Failed Solder Connection on HPCI Flow.Solder Connection Repaired
05000277/LER-1995-006, :on 951022,offsite Electrical Power Source Lost.Caused by Momentary Deenergization of Several Electrical Distribution Panels.Isolation Logics Reset & Affected Sys Restored
05000277/LER-1996-006-01, :on 960522,Unit 2 RPS Power Supply Unexpectedly Lost.Caused by Human Performance.Rps Bus Supply Restored & Operator Involved in Event Coached on self-checking Practices.W/Undated Ltr
05000277/LER-1996-003-01, :on 960228,ESFA Occurred Due to Loss of One off-site Power Source.Reset PCIS Group II Isolation Logics & Restored Affected Sys.W/Undated Ltr
05000277/LER-1996-002-01, :on 960126,TS Violation Occurred When Certain Emergency Bus Protection Relays Found Out of Calibr Due to Inadequate Testing Methodology.Recalibrated Affected Relays to within Appropriate TS Limits
05000277/LER-1996-001-01, :on 960118,licensed Thermal Power Slightly Exceeded Due to Unaccounted for CRD Water Flow.Caused by Failure to Consider Impact of Addl Flow on Core Thermal Power.Mod Design Process Will Be Enhanced.W/Undated Ltr
05000278/LER-1995-007-02, :on 951202,main Turbine Trip Occurred Caused by Full Reactor Scram.Replaced Mechanical Trip Solenoid Valve Terminal Strip That Caused Initial Ground
05000278/LER-1995-005-03, :on 951108,three of Eleven MSRVs Did Not Lift within TS +1% Tolerance Due to Small Drift in Setpoint of Valves.Refurbished Valves Have Been Properly Setup at Test Facility & Install for All MSRVs & SVs
05000278/LER-1995-004-03, :on 951028,drywell Floor Drain & Equipment Sump Pump Was in TS Violation.Caused by Both Floor & Equipment Drain Sump Pumps Not Operating in Automatic Mode.Provided Pertinent Info from Event to Personnel
05000278/LER-1995-006-03, :on 951025,TS Violation Occurred Due to Licensed Reactor Power Exceeded.Corrected Program That Calculates TS 8 H Shift Average CTP
05000277/LER-1995-006-02, :on 951022,transfer of Startup Circuits Resulted in PCIS Group II Half Isolation on Both Units Due Loss of One Offsite Power Source.Pcis Group II Isolation Logics Reset & Affected Sys Restored.W/Undated Ltr
05000277/LER-1995-005-02, :on 950922,discovered That Narrow Range Indication on Dwl Pr (PR-2(3)508) Being Checked Instead of Wide Range Indicator Required by Ts.Surveillance Tests Associated W/Monitoring Parameters Changed.W/Undated Ltr
05000277/LER-1995-003-03, :on 950815,unplanned ESF Actuation Occurred When Wire Was Out in Junction Box.Evaluated Addl Labelling & Print Revs
05000277/LER-1995-004-02, :on 950814,TS Violation Occurred When RWCU Temp Switch Was Inoperable Due to Design Deficiency.Revised Calibr Sheet for TIS-2-12-099 to Add Note to Ensure Proper Installation of Thermistor
05000278/LER-1995-003-02, :on 950730,Unit 3 Scram Occurred When a Reactor Feed Pump Speed Increased.Caused by High Reactor Water Level Condition.Reset Appropriate PCIS & RPS Scram Logics
05000277/LER-1995-001-03, :on 950609,E-2 DG Output Breaker Tripped Open. Loss of Power to 4kV Bus Caused Group II & III Isolation. Caused by Inadequate Review of Routine Test RT-0-052-252-2. PCIS Logic Reset & Affected Sys Restored.W/Undated Ltr
05000278/LER-1995-002-02, :on 950706,HPCI Steam Admission Valve (MO-3-23-14) Failed to Fully Open When Given Initiation Signal.Caused by Failure of Operator Motor.Operator Motor Replaced.W/Undated Ltr
05000277/LER-1995-002-01, :on 950618,condition Was Prohibited by TS When Two DGs Inoperable at Same Time Due to 59G Relay Issue. Corrected Wiring Discrepancy on E-2D/G & Completed Performance of Post Maint Test
05000278/LER-1995-001-02, :on 950323,Unit 3 Scram on Low Condenser Vacuum Due to Loss of Steam Jet Air Ejector.Scram & PCIS Group Ii/Iii Isolation Logics Were Reset
05000277/LER-1994-009-01, :on 940921,six Valves Associated W/Primary Containment Isolation Sys Group II Isolation Logic Closed. Caused by Lifting Common Neutral Lead on Relay 16A-K63 Part of PM Activity.Pcis Valves Replaced.W/Undated Ltr
05000277/LER-1994-010-02, :on 941024,setpoint Drift Associated W/Main Steam Relief Valves & Safety Valves Occurred.Caused by Small Drift in Setpoint of Valves.Refurbished Valves Properly Setup at Test Facility & Installed
05000278/LER-1994-005-03, :on 941011,Unit 3 Scram Occurred Due to Static Inverter Failure.Appropriate PCIS & RPS Scram Logic Reset & Affected Sys Reset to Appropriate Configuration & Failed Unit 3 Transformer Replaced & Properly Setup
05000278/LER-1994-004-02, :on 940924,HPIS Inoperable When Steam Supply Valve Was Closed to Isolate Leak.Caused by Packing Leak on MO-3-23-15.Corrective Actions Being Developed.W/Undated Ltr
05000277/LER-1994-008-02, :on 940909,discovered That ECCS & EDG May Have Been TS Inoperable on 940803 When ESW Outlet Valve MO-0498 Closed & Left Unattended,Causing ECT to Overflow.Valve Opened & ECT Level Restored to Normal Range.W/Undated Ltr
05000278/LER-1994-003-03, :on 940811,HPCI System Was Considered Inoperable & Was Placed in Secured Condition by Reactor Operator.Caused by Individuals Incorrectly Deciding to Work on CR Relay.Hpci System Was Restored
05000277/LER-1994-007-02, :on 940810,secondary Containment Breached to Fight Fire Inside Unit 2 Vent Stack Protective Siding.Caused by Work Area Not Being Properly Staged.Fire Promptly Extinguished & Secondary Containment Restored
05000277/LER-1994-006-02, :on 940804,no Firewatches Were in Areas During 50 Minute Period When Carbon Dioxide Fire Suppression Sys Was Inoperable.Caused by Inadequate Communication.Involved Individual Has Been Counselled
05000277/LER-1994-005-02, :on 940722,actual Torus Water Level Less than That Indicated on Narrow Range Instrumentation.Initial Ref Marking Used to Support Calibr Activities Not Correct
05000277/LER-1994-004-01, :on 940718,HPCI System Was Declared Inoperable. Caused by Problem W/Hpci Signal Isolator.Signal Isolating Device XS-2-23-144 Removed & Replaced
05000277/LER-1994-002, :on 940421,determined That Sample Lines on Systems Became Plugged Due to Build Up of Silt from River Water.Sample Lines Were Flush & Systems Were Returned to Service
05000278/LER-1993-007, :on 930820,identified That Stated Surveillance Test Not Performed Prior to Exceeding TS Out of Surveillance Date,Resulting in Violation on 930808.Caused by Inadequate Review.Personnel to Be Counselled
05000277/LER-1994-003-01, :on 940515,Unit 2 Scram on High Neutron Flux Condition Occurred Due to Unexpected Speed Increase on 2A Recirc Pump.Restored & Reset PCIS & RPS Scram Logics
05000277/LER-1994-002-03, :on 940426,confirmed That Circulating Water Intake Composite Sampler Sys Not Properly Functioning.Caused by Small Valve on Sys That Became Plugged.Composite Sample Valve & Line Flushed
05000278/LER-1994-002-01, :on 940203,discovered Main Generator Ground Relay Status Light Out.Caused by Internal Rack Out Tab Not Installed on Alterex Field Breaker.Damaged Component Repaired & Breaker Replaced W/Spare
05000278/LER-1994-001, :on 940124,HPCI Sys Declared Inoperable During Performance of Quarterly Surveillance Test.Caused by Leak on HPCI Sys Hydraulic Control Line.Hydraulic Control Line Repaired & HPCI Sys Tested
05000277/LER-1993-016-01, :on 931221,HPCIS Declared Inoperable During Performance of Surveillance Test.Cause Not Yet Determined. Instument Caibration Line Flushed to Clear Blockage & Back Filled.Procedures Revised
05000277/LER-1993-015-01, :on 931201,TS Violation Occurred Due to Improperly Secured Main Stack Particulate Filter.Filters Changed & Gas Marnelli Samples Obtained to Identify & Quantify Nuclides in Main Stack Effluent
05000278/LER-1993-010-03, :on 931201,TS Required Shutdown Initiated Due to Failed Residual Heat Removal Sys Valve.Caused by Bent Valve Stem on MO-3-10-025A.RHR Loop Injection Valve Was Dissassembled & New Valve Stem Installed
05000278/LER-1993-008-03, :on 931018,identified That Two of Eleven MSRVs & One of Two SVs Did Not Lift within TS Plus or Minus 1% Tolerence Due to Small Drift in Setpoint of Valves.Ts Change Request Being Evaluated
05000277/LER-1993-014, :on 931006,discovered Crev Control Switches in Off Instead of Auto Position.Caused by Poor Communication Between Plant Personnel.Control Switches Properly Aligned
05000278/LER-1993-009-03, :on 931113,HPCI Sys Declared Inoperable When Discharge Valve Would Not Open Due to Misaligned Relay Contact.Following Relay adjustment,MO-3-23-19 Tested Satisfactorily & Associated TS LCO Exited
05000278/LER-1993-006-02, :on 930814,LPCI Sys Became Inoperable When Triple Low Water Level Signal Simulated on Unit 2.RWL Instrumentation LT-72B Valved Out of Svc & Equalized Allowing Indicated Water Level to Increase
05000278/LER-1993-005-02, :on 930809,HPCI Sys Declared Inoperable Due to Defective Flow Controller.Flow Controller Removed,All Potentiometers & Boards Cleaned,Flow Controller Reinstalled & Necessary Testing & Tuning Performed
05000278/LER-1993-004-03, :on 930730,simulated Low Steam Flow Signal to Recombiner Initiated Isolation Signal to Off Gas Recombiner, Causing Main Condenser Vacuum to Begin Decreasing.Special Procedure SP-1438 Revised
05000277/LER-1993-012, :on 930607,discovered That Surveillance Test on Fire Protection Sys Missed on 930601.Caused by Insufficient Degree of Attention Applied by Nonlicensed Individual.Test Satisfactorily Completed
05000277/LER-1993-011, :on 930528,TS Violation Occurred When New Fuel Was Added to EDG Fuel Oil Storage Tank Prior to Completion of Chemical Analysis.Caused by Personnel Error.Individual Counselled
05000277/LER-1993-013, Forwards LER 93-013-00.LER Originally Distributed to All Individuals & Organizations Except DCD Due to Administrative Oversight