| | | Reporting criterion |
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| 05000530/LER-1993-001-02, :on 930204,reactor Trip Occurred Due to SG 2 Water Level Reaching RPS Trip Setpoint for Low SG Water Level Following Loss of Main Feedwater Pump A.Caused by Failure of Circuit Board.Investigation Underway |
- on 930204,reactor Trip Occurred Due to SG 2 Water Level Reaching RPS Trip Setpoint for Low SG Water Level Following Loss of Main Feedwater Pump A.Caused by Failure of Circuit Board.Investigation Underway
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2) |
| 05000530/LER-1993-001, Forwards LER 93-001-00 Re Reactor Trip Which Occurred Following Failure of Main Feedwater Pump a & Resultant ESFAS Actuations.Ler Also Serves as Special Rept Describing Circumstances of ECCS Actuation | Forwards LER 93-001-00 Re Reactor Trip Which Occurred Following Failure of Main Feedwater Pump a & Resultant ESFAS Actuations.Ler Also Serves as Special Rept Describing Circumstances of ECCS Actuation | |
| 05000528/LER-1993-001, Corrected Ltr Forwarding LER 93-001-00,containing Rept Date & Correct Page Numbers.Ler Discusses Manual Reactor Trip as Result of Automatic Main Turbine Trip | Corrected Ltr Forwarding LER 93-001-00,containing Rept Date & Correct Page Numbers.Ler Discusses Manual Reactor Trip as Result of Automatic Main Turbine Trip | |
| 05000528/LER-1993-001-01, :on 930130,main Turbine Trip Occurred Which Initiated Manual Reactor Trip After Receiving High Pressurizer Pressure Pretrip Alarm.Caused by Failure of High Tank Level Controller.Failed Controller Replaced |
- on 930130,main Turbine Trip Occurred Which Initiated Manual Reactor Trip After Receiving High Pressurizer Pressure Pretrip Alarm.Caused by Failure of High Tank Level Controller.Failed Controller Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2) |
| 05000529/LER-1993-001-03, :on 930314,reactor Manually Tripped Following Steam Generator Tube Rupture.Investigation Team Formed & Investigation Initiated Per Incident Investigation Program. Results Will Be Provided in Supplemental LER |
- on 930314,reactor Manually Tripped Following Steam Generator Tube Rupture.Investigation Team Formed & Investigation Initiated Per Incident Investigation Program. Results Will Be Provided in Supplemental LER
| |
| 05000529/LER-1993-001, :on 930314,SG Tube Ruptured in SG 2.Caused by Iga/Isgcc Occurring as Result of Tube to Tube Crevice Formation.Implemented Changes to EOP |
- on 930314,SG Tube Ruptured in SG 2.Caused by Iga/Isgcc Occurring as Result of Tube to Tube Crevice Formation.Implemented Changes to EOP
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1993-002, Forwards LER 93-002-00 Re Discovery That Design Basis Fire in Control Room,Concurrent W/Loss of Offsite Power Could Result in Loss of Control Room Power to Train B DG Output Breaker & Essential Exhaust Fan Breaker | Forwards LER 93-002-00 Re Discovery That Design Basis Fire in Control Room,Concurrent W/Loss of Offsite Power Could Result in Loss of Control Room Power to Train B DG Output Breaker & Essential Exhaust Fan Breaker | |
| 05000529/LER-1993-002-01, :on 930518,determined That 15 Out of 20 MSSV & Pressure Safety Valves Out of Tolerence Limit Specified in TS 3.7.1.1 & 3.4.2.2.Cause of Setpoint Drift Being Investigated.Valve Setpoints Readjusted |
- on 930518,determined That 15 Out of 20 MSSV & Pressure Safety Valves Out of Tolerence Limit Specified in TS 3.7.1.1 & 3.4.2.2.Cause of Setpoint Drift Being Investigated.Valve Setpoints Readjusted
| 10 CFR 50.73(a)(2) |
| 05000529/LER-1993-002, :on 930518,determined That 15 of 20 MSSV & 4 of 4 Pressurizer Safety Valves as-found Relief Settings Out of Tolerence Limits.Valves Exhibited Seat Wear.Efforts to Enhance MSSV Setpoint Repeatability Continuing |
- on 930518,determined That 15 of 20 MSSV & 4 of 4 Pressurizer Safety Valves as-found Relief Settings Out of Tolerence Limits.Valves Exhibited Seat Wear.Efforts to Enhance MSSV Setpoint Repeatability Continuing
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) |
| 05000528/LER-1993-003, :on 930213,normal Supply Breaker to non-Class 1E 13.8 Kv Intermediate Bus Opened on Overcurrent,Resulting in Loss of Power to Train A.Caused by Insulation Breakdown on Breaker Bushing.Damaged Breaker Removed |
- on 930213,normal Supply Breaker to non-Class 1E 13.8 Kv Intermediate Bus Opened on Overcurrent,Resulting in Loss of Power to Train A.Caused by Insulation Breakdown on Breaker Bushing.Damaged Breaker Removed
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1993-003-01, Forwards LER 93-003-01,providing Addl Info on Root Cause of Failure & Component Failure Data | Forwards LER 93-003-01,providing Addl Info on Root Cause of Failure & Component Failure Data | |
| 05000528/LER-1993-004, :on 930520,ASME Section XI Testing of Charging Pumps Not in Compliance W/Code Requirements Due to Personnel Error.C/As:Testing in Accordance W/Asme Section XI Code Requirements |
- on 930520,ASME Section XI Testing of Charging Pumps Not in Compliance W/Code Requirements Due to Personnel Error.C/As:Testing in Accordance W/Asme Section XI Code Requirements
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(5) |
| 05000530/LER-1993-004-01, :on 931103,reactor Manually Tripped After Recognizing That Subgroup 5 of CEA Regulating Group 4 Slipped Into Reactor Core During Reactor Power Reduction. CEA Regulating Group 4 Will Be Monitored |
- on 931103,reactor Manually Tripped After Recognizing That Subgroup 5 of CEA Regulating Group 4 Slipped Into Reactor Core During Reactor Power Reduction. CEA Regulating Group 4 Will Be Monitored
| |
| 05000529/LER-1993-005, :on 931123,identified That SR 4.8.1.1.1.a Which Verifies Operability of Ac Offsite Sources Not Completed within Required Time (1 H) Due to Cognitive Personnel Error. Surveillance Completed W/No Problems on 931123 |
- on 931123,identified That SR 4.8.1.1.1.a Which Verifies Operability of Ac Offsite Sources Not Completed within Required Time (1 H) Due to Cognitive Personnel Error. Surveillance Completed W/No Problems on 931123
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(e)(2) |
| 05000529/LER-1993-005-01, :on 931123,identified That SR 4.8.1.1.1.a Had Not Been Completed within Required 1 H Timeframe.Caused by Personnel Error.Required Surveillance Completed Satisfactorily on 931123 |
- on 931123,identified That SR 4.8.1.1.1.a Had Not Been Completed within Required 1 H Timeframe.Caused by Personnel Error.Required Surveillance Completed Satisfactorily on 931123
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1993-005, :on 920728,identified That Redundant Trains of Safe Shutdown Equipment Could Be Rendered Inoperable by Single Fire.Fire Watches Manned in Any Area Not Already Under Conpensatory Fire Watch |
- on 920728,identified That Redundant Trains of Safe Shutdown Equipment Could Be Rendered Inoperable by Single Fire.Fire Watches Manned in Any Area Not Already Under Conpensatory Fire Watch
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2) |
| 05000530/LER-1993-005-02, :on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action Issued |
- on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action Issued
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2) |
| 05000528/LER-1993-006-01, Forwards LER 93-006-01,providing Addl Info on Status of Unit 2 During Event | Forwards LER 93-006-01,providing Addl Info on Status of Unit 2 During Event | |
| 05000528/LER-1993-006, :on 930505,determined That Original Design of Shutdown Suction Isolation Valve Motor Control Circuits May Not Meet Requirements for Overload Protection Bypass.Cause Under Investigation.Lco 3.8.4.2 Entered & Mods Completed |
- on 930505,determined That Original Design of Shutdown Suction Isolation Valve Motor Control Circuits May Not Meet Requirements for Overload Protection Bypass.Cause Under Investigation.Lco 3.8.4.2 Entered & Mods Completed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2) |
| 05000528/LER-1993-007, :on 930512,concluded That TS SR 4.7.9.e Incorrectly Interpreted.Pvngs Snubber Testing Program Will Be Revised to Correctly Implement TS Requirements Prior to Commencing Next Testing Cycle |
- on 930512,concluded That TS SR 4.7.9.e Incorrectly Interpreted.Pvngs Snubber Testing Program Will Be Revised to Correctly Implement TS Requirements Prior to Commencing Next Testing Cycle
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1993-007-02, Corrected Ltr Forwarding LER 93-007-02,changing Corrective Action Due Date to Coincide W/Reply to Notice of Violation 50-528/93-12-04.W/o Encl | Corrected Ltr Forwarding LER 93-007-02,changing Corrective Action Due Date to Coincide W/Reply to Notice of Violation 50-528/93-12-04.W/o Encl | |
| 05000528/LER-1993-008, :on 930224,gaseous Radwaste Sys Oxygen Monitor Out of Svc for 18 Days Due to Random Component Failure. Updated Grs Explosive Gas Monitoring Sys |
- on 930224,gaseous Radwaste Sys Oxygen Monitor Out of Svc for 18 Days Due to Random Component Failure. Updated Grs Explosive Gas Monitoring Sys
| |
| 05000528/LER-1993-009, :on 931022,determined That 18 of 20 MSSVs & 4 of 4 Pressurizer Safety Valves Setpoints (Psv) Out of Tolerence Due to Setpoint Drift.Mssvs & Psvs Lift Setpoints Adjusted within TS Limits |
- on 931022,determined That 18 of 20 MSSVs & 4 of 4 Pressurizer Safety Valves Setpoints (Psv) Out of Tolerence Due to Setpoint Drift.Mssvs & Psvs Lift Setpoints Adjusted within TS Limits
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(5) |
| 05000528/LER-1993-010, :on 931105,determined That,In Past,Capability of Number of MOVs to Perform Intended Safety Function,Under Design Basis Condition Questionable.Planned Testing of MOVs to Meet GL 89-10 Performance Criteria Expected to Continue |
- on 931105,determined That,In Past,Capability of Number of MOVs to Perform Intended Safety Function,Under Design Basis Condition Questionable.Planned Testing of MOVs to Meet GL 89-10 Performance Criteria Expected to Continue
| |
| 05000528/LER-1993-011, Forwards Suppl 1 to LER 93-011 Per 10CFR50.73,reporting That Addl Undervoltage Scenario Has Been Identified That Could Result in Possible Double Sequencing of SR Equipment | Forwards Suppl 1 to LER 93-011 Per 10CFR50.73,reporting That Addl Undervoltage Scenario Has Been Identified That Could Result in Possible Double Sequencing of SR Equipment | |
