| | | Reporting criterion |
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| 05000443/LER-1992-001-01, :on 920129,auxiliary Sample Pump Not Operating as Indicated by Lack of Sample Flow.Caused by Equipment Failure.Cooling Fan Connection Was Corrected & Procedure Change Will Be Submitted |
- on 920129,auxiliary Sample Pump Not Operating as Indicated by Lack of Sample Flow.Caused by Equipment Failure.Cooling Fan Connection Was Corrected & Procedure Change Will Be Submitted
| 10 CFR 50.73(a)(2)(i) |
| 05000443/LER-1992-002, Forwards License Amend Request 92-12 to License NPF-86, Changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates,Per LER 92-02-00 | Forwards License Amend Request 92-12 to License NPF-86, Changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates,Per LER 92-02-00 | |
| 05000443/LER-1992-003, :on 920309,determined That Integrity of Concrete Structure Which Encls Condensate Storage Tank Not Verified Once Per 12 H on 901222,910512 & 1109.Caused by Failure to Follow Procedures |
- on 920309,determined That Integrity of Concrete Structure Which Encls Condensate Storage Tank Not Verified Once Per 12 H on 901222,910512 & 1109.Caused by Failure to Follow Procedures
| |
| 05000443/LER-1992-004, :on 920325,discrepancy Identified W/Manner in Which Valve Closure Stroke Time Testing Performed for 20 Valcor solenoid-operated Valves.Caused by Design & Testing Inadequacies.Design Change Implemented |
- on 920325,discrepancy Identified W/Manner in Which Valve Closure Stroke Time Testing Performed for 20 Valcor solenoid-operated Valves.Caused by Design & Testing Inadequacies.Design Change Implemented
| 10 CFR 50.73(u)(2)(1) |
| 05000443/LER-1992-005, :on 920529,two Out of Three Pressure Code Safety Valves Failed Required Setpoint Testing.Caused by Leakage in 1 Valve & Cause Unknown in Other Valve.Valves Retested & Reworked as Needed |
- on 920529,two Out of Three Pressure Code Safety Valves Failed Required Setpoint Testing.Caused by Leakage in 1 Valve & Cause Unknown in Other Valve.Valves Retested & Reworked as Needed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000443/LER-1992-006, :on 920612,smoke Detector in Control Room East Air Intake Actuated High Smoke Concentration Alarm.Caused by Spurious Alarm Signal Due to Adverse Environ Conditions.Work Request Initiated to Recalibr Detector |
- on 920612,smoke Detector in Control Room East Air Intake Actuated High Smoke Concentration Alarm.Caused by Spurious Alarm Signal Due to Adverse Environ Conditions.Work Request Initiated to Recalibr Detector
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-1992-007, :on 920617,A Train Containment Encl Emergency Air Cleanup Sys Discovered Inoperable Due to Personnel Error.Appropriate TS Statement Entered & Inoperable Equipment Returned to Operable Status |
- on 920617,A Train Containment Encl Emergency Air Cleanup Sys Discovered Inoperable Due to Personnel Error.Appropriate TS Statement Entered & Inoperable Equipment Returned to Operable Status
| 10 CFR 50.73(a)(2)(i) |
| 05000443/LER-1992-008, :on 920626,determined That 18-month Surveillance Test Program for EDG Inadequately Tested Undervoltage Circuitry,Per NRC Info Notice 92-040.Caused by Misinterpretation of Testing Requirements |
- on 920626,determined That 18-month Surveillance Test Program for EDG Inadequately Tested Undervoltage Circuitry,Per NRC Info Notice 92-040.Caused by Misinterpretation of Testing Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000443/LER-1992-009, :on 920729,determined That 18-month Surveillance Testing Program for Reactor Trip Breakers & Reactor Trip Bypass Breakers Did Not Test Shunt Trip Circuits.Caused by Inadequate Procedure |
- on 920729,determined That 18-month Surveillance Testing Program for Reactor Trip Breakers & Reactor Trip Bypass Breakers Did Not Test Shunt Trip Circuits.Caused by Inadequate Procedure
| |
| 05000443/LER-1992-010, :on 920703,portable Air Compressor Utilized for Sandblasting Operations Caught Fire in CR Ventilation Sys. Caused by Inadequate Procedural Guidance.Design Basis & Operability Requirements Revised |
- on 920703,portable Air Compressor Utilized for Sandblasting Operations Caught Fire in CR Ventilation Sys. Caused by Inadequate Procedural Guidance.Design Basis & Operability Requirements Revised
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000443/LER-1992-011, :on 920807,identified That Operability of Svc Water Cooling Tower Had Not Been Adequately Demonstrated,Per TS Surveillance Requirement 4.7.5.d.1.Caused by Inadequate Review by Licensee.Procedures Revised |
- on 920807,identified That Operability of Svc Water Cooling Tower Had Not Been Adequately Demonstrated,Per TS Surveillance Requirement 4.7.5.d.1.Caused by Inadequate Review by Licensee.Procedures Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 05000443/LER-1992-012, :on 920826,ESF Actuation Occurred,Causing SG Blowdown to Isolate.Caused by Personnel Failing to Follow Procedures for Surveillance Activities.Written Guidance Issued Re Specifying Function of Each Jumper |
- on 920826,ESF Actuation Occurred,Causing SG Blowdown to Isolate.Caused by Personnel Failing to Follow Procedures for Surveillance Activities.Written Guidance Issued Re Specifying Function of Each Jumper
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-1992-013-01, Forwards LER 92-013-01 Re Tornado Design of Plant Doors. Submittal Documents Root Cause & Corrective Actions Ongoing at Time of LER 92-013-00 Submittal | Forwards LER 92-013-01 Re Tornado Design of Plant Doors. Submittal Documents Root Cause & Corrective Actions Ongoing at Time of LER 92-013-00 Submittal | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000443/LER-1992-013, :on 920827,determined That Six Plant Doors Did Not Have Tornado Design to Withstand Differential Pressure, Per Updated Fsar.Caused by Failure to Include Doors in United Engineers & Constructors Spec.Updated FSAR Revised |
- on 920827,determined That Six Plant Doors Did Not Have Tornado Design to Withstand Differential Pressure, Per Updated Fsar.Caused by Failure to Include Doors in United Engineers & Constructors Spec.Updated FSAR Revised
| 10 CFR 50.73(a)(2) |
| 05000443/LER-1992-014, :on 920901,missed TS Surveillance on Seismic Monitoring Instrumentation Missed.Caused by Inadequate Communication.Operating Mgr Will Review Event W/Each Operating Crew & W/Work Control Supervisor |
- on 920901,missed TS Surveillance on Seismic Monitoring Instrumentation Missed.Caused by Inadequate Communication.Operating Mgr Will Review Event W/Each Operating Crew & W/Work Control Supervisor
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000443/LER-1992-015, :on 920902,during Walkdown for IPE for External Events,Discovered That Scupper in Svc Water Pumphouse Roof Parapet Not Covered by Roofing Matl.Cause Indeterminate. Roofing Matl Covering Scuppers Removed |
- on 920902,during Walkdown for IPE for External Events,Discovered That Scupper in Svc Water Pumphouse Roof Parapet Not Covered by Roofing Matl.Cause Indeterminate. Roofing Matl Covering Scuppers Removed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000443/LER-1992-016, :on 920904,determined That Results for 920904 & 05 MSSV Setpoint Test,Indicated That Nine MSSVs Outside Acceptance Criteria in TS 3.7.1.1.Caused by Metallurgical Bonding.Six of Nine MSSVs Reset |
- on 920904,determined That Results for 920904 & 05 MSSV Setpoint Test,Indicated That Nine MSSVs Outside Acceptance Criteria in TS 3.7.1.1.Caused by Metallurgical Bonding.Six of Nine MSSVs Reset
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) |
| 05000443/LER-1992-017, :on 920907,SG Level Oscillations Occurred in One Sg,Resulting in Overfed SG & Causing High SG Level Alarm.Caused by Incomplete Communications.Personnel Will Critique Event & Training Program Reviewed |
- on 920907,SG Level Oscillations Occurred in One Sg,Resulting in Overfed SG & Causing High SG Level Alarm.Caused by Incomplete Communications.Personnel Will Critique Event & Training Program Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-1992-018, :on 920915,RCP Cubicle Found W/O Controls Required by TS 6.11, High Radiation Area. Caused by Lack of Attention to Detail.Induividuals Directed to Leave Area & RWP Corrected |
- on 920915,RCP Cubicle Found W/O Controls Required by TS 6.11, High Radiation Area. Caused by Lack of Attention to Detail.Induividuals Directed to Leave Area & RWP Corrected
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000443/LER-1992-019-01, Forwards LER 92-019-01 Re Delta T/Tavg Protection Channel Operational Test,Documenting Root Cause & Corrective Actions,Per Evaluation Ongoing at Time of LER 92-019-00 Submittal | Forwards LER 92-019-01 Re Delta T/Tavg Protection Channel Operational Test,Documenting Root Cause & Corrective Actions,Per Evaluation Ongoing at Time of LER 92-019-00 Submittal | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000443/LER-1992-019, :on 920916,determined That Procedures for Performing Delta T/Tavg Protection Channel Operational Test Inadequate Due to Lack of Complete Technical Review of I&C Procedures.Appropriate Procedures Revised |
- on 920916,determined That Procedures for Performing Delta T/Tavg Protection Channel Operational Test Inadequate Due to Lack of Complete Technical Review of I&C Procedures.Appropriate Procedures Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000443/LER-1992-020, :on 921005,determined That 24 H Sample Interval for Train B Pcc Water Sys Taken Out of Svc on 920924 Exceeded by One H & 25 Minutes.Caused by Personnel Error. Responsible Personnel Counseled |
- on 921005,determined That 24 H Sample Interval for Train B Pcc Water Sys Taken Out of Svc on 920924 Exceeded by One H & 25 Minutes.Caused by Personnel Error. Responsible Personnel Counseled
| 10 CFR 50.73(a)(2)(i) |
| 05000443/LER-1992-021, :on 921018,discovered Motor Circuit Breaker for Nonoperating Centrifugal Charging Pump Connected to Electrical Bus Prior to Closing & Locking Pump Discharge Valve.Caused by Operator Error |
- on 921018,discovered Motor Circuit Breaker for Nonoperating Centrifugal Charging Pump Connected to Electrical Bus Prior to Closing & Locking Pump Discharge Valve.Caused by Operator Error
| |
| 05000443/LER-1992-022, :on 921110,determined That Containment Personnel Hatch Airlock Seal Leakage Surveillance Not Performed at TS-required Frequencies.Caused by Lack of Administrative Mechanism.Package Generated |
- on 921110,determined That Containment Personnel Hatch Airlock Seal Leakage Surveillance Not Performed at TS-required Frequencies.Caused by Lack of Administrative Mechanism.Package Generated
| 10 CFR 50.73(a)(2)(1) |
| 05000443/LER-1992-023, :on 921112 & 16,three safety-related Components,Within Scope of IST Program,Not Tested Prior to Entry Into Mode 4.Caused by Personnel & Procedure Error. Using Proper Documentation Will Be Stressed |
- on 921112 & 16,three safety-related Components,Within Scope of IST Program,Not Tested Prior to Entry Into Mode 4.Caused by Personnel & Procedure Error. Using Proper Documentation Will Be Stressed
| |
| 05000443/LER-1992-024, :on 921127,reactor Trip Occurred Due to Spurious Signal in RCS Overpower Delta T Protection Circuit.Caused by Erratic Setpoint Voltage from Circuit Card.Faulty Circuit Card Replaced |
- on 921127,reactor Trip Occurred Due to Spurious Signal in RCS Overpower Delta T Protection Circuit.Caused by Erratic Setpoint Voltage from Circuit Card.Faulty Circuit Card Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-1992-025, :on 921213,manual Reactor Trip Initiated Due to Unavailability of Two Circulating Water Sys Pumps.Temporary Mod Installed to Allow for Continuous Manual Operation of Traveling Screens at Either Slow or Fast Speed |
- on 921213,manual Reactor Trip Initiated Due to Unavailability of Two Circulating Water Sys Pumps.Temporary Mod Installed to Allow for Continuous Manual Operation of Traveling Screens at Either Slow or Fast Speed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000443/LER-1992-026, :on 920714,discovered That Three of Four Cover Bolts on Resin Sluice Discharge Valve Fractured,Resulting in Loosening of Valve Bonnet.Caused by High Matl Hardness.Bolts in Plug Valves Replaced |
- on 920714,discovered That Three of Four Cover Bolts on Resin Sluice Discharge Valve Fractured,Resulting in Loosening of Valve Bonnet.Caused by High Matl Hardness.Bolts in Plug Valves Replaced
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) |