05000336/LER-1999-012, :on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated1999-10-15015 October 1999
- on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated
05000336/LER-1999-011, :on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures1999-09-20020 September 1999
- on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures
05000245/LER-1999-001-02, :on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With1999-09-0808 September 1999
- on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With
05000336/LER-1999-010, :on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators1999-09-0202 September 1999
- on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators
05000423/LER-1999-007-01, :on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With1999-06-17017 June 1999
- on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With
05000423/LER-1999-006-01, :on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly1999-06-15015 June 1999
- on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly
05000423/LER-1999-004-01, :on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With1999-06-14014 June 1999
- on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With
05000423/LER-1999-005-01, :on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed1999-06-0808 June 1999
- on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed
05000423/LER-1999-003-01, :on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With1999-06-0404 June 1999
- on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With
05000336/LER-1999-001, :on 990106,discovered That One of Rated Fire Doors Has Not Been Properly Surveilled.Caused by Double Door Being Improperly Labeled.Design Change Will Replace Door with 3-hour Rated Fire Door.With1999-02-0101 February 1999
- on 990106,discovered That One of Rated Fire Doors Has Not Been Properly Surveilled.Caused by Double Door Being Improperly Labeled.Design Change Will Replace Door with 3-hour Rated Fire Door.With
05000336/LER-1998-026-01, :on 981223,discovered That Pressurizer Spray Line Fatigue Limits Were Exceeded.Caused by Insufficient Thermal Effects Analysis.Design Mods Will Be Implemented to Ensure Compliance with ASME Code Requirements1999-01-21021 January 1999
- on 981223,discovered That Pressurizer Spray Line Fatigue Limits Were Exceeded.Caused by Insufficient Thermal Effects Analysis.Design Mods Will Be Implemented to Ensure Compliance with ASME Code Requirements
05000336/LER-1998-025-01, :on 981111,noted That Several Check Valves Had Not Been Tested IAW ASME Section XI Criterion.Caused by Inadequate Design Basis Flow Requirement Specifications for IST Check Valves.Applicable IST Sps Will Be Revised1999-01-12012 January 1999
- on 981111,noted That Several Check Valves Had Not Been Tested IAW ASME Section XI Criterion.Caused by Inadequate Design Basis Flow Requirement Specifications for IST Check Valves.Applicable IST Sps Will Be Revised
05000336/LER-1998-012-01, :on 980521,nonconservative Assumptions in Facility Loss of Normal FW Analysis Occurred.Caused by Incorrect Calculation of SG Inventory During Loss of Normal FW Event.Reanalysis of FSAR Loss of Normal FW Completed1998-12-23023 December 1998
- on 980521,nonconservative Assumptions in Facility Loss of Normal FW Analysis Occurred.Caused by Incorrect Calculation of SG Inventory During Loss of Normal FW Event.Reanalysis of FSAR Loss of Normal FW Completed
05000336/LER-1998-024-01, :on 981030,potential Leakage Path Through Containment Pressure Instrument Was Identified.Caused by Failure to Adequately Consider FSAR Design Commitments. Replaced Nonconforming Containment Pressure Instruments1998-11-25025 November 1998
- on 981030,potential Leakage Path Through Containment Pressure Instrument Was Identified.Caused by Failure to Adequately Consider FSAR Design Commitments. Replaced Nonconforming Containment Pressure Instruments
05000336/LER-1998-023-01, :on 980924,failed to Adequately Test CAR Fans IAW TS SR 4.6.2.1.2(a).Caused by Misinterpretation of SR 4.6.2.1.2(a).Surveillance Procedures Were Revised to Ensure Periodic Testing of CAR Fans Satisfies SR 4.6.2.1.2(a)1998-11-13013 November 1998
- on 980924,failed to Adequately Test CAR Fans IAW TS SR 4.6.2.1.2(a).Caused by Misinterpretation of SR 4.6.2.1.2(a).Surveillance Procedures Were Revised to Ensure Periodic Testing of CAR Fans Satisfies SR 4.6.2.1.2(a)
05000336/LER-1998-020-01, :on 980929,noted SI Recirculation Header Piping Components Did Not Fully Satisfy ISI Requirements.Caused by Lack of ISI Test Program Ownership.Revised Applicable SI Leakage Test Procedure1998-10-16016 October 1998
- on 980929,noted SI Recirculation Header Piping Components Did Not Fully Satisfy ISI Requirements.Caused by Lack of ISI Test Program Ownership.Revised Applicable SI Leakage Test Procedure
05000336/LER-1998-021-01, :on 980825,noted Inadequate Radiation Monitoring of Containment Atmosphere During Refueling Operations.Caused by Failure to Reflect Design Basis Assumptions Into Operating Practices.Will Revise Procedure1998-10-0808 October 1998
- on 980825,noted Inadequate Radiation Monitoring of Containment Atmosphere During Refueling Operations.Caused by Failure to Reflect Design Basis Assumptions Into Operating Practices.Will Revise Procedure
05000336/LER-1998-019-01, :on 980826,potential Inability to Close AFW Regulator Valves After HELB Discovered.Caused by Inadequate Review by Original Facility Analysis for Postulated Helbs.Afw Sys Will Be Upgraded1998-09-25025 September 1998
- on 980826,potential Inability to Close AFW Regulator Valves After HELB Discovered.Caused by Inadequate Review by Original Facility Analysis for Postulated Helbs.Afw Sys Will Be Upgraded
05000336/LER-1998-018-01, :on 980818,spatial Separation of Redundant Cable Trays Did Not Meet Min Design Requirements.Caused by Initial Inadequate Installation.Data Is Being Evaluated from Walkdowns of Other Vital Equipment Cable Tray Areas1998-09-16016 September 1998
- on 980818,spatial Separation of Redundant Cable Trays Did Not Meet Min Design Requirements.Caused by Initial Inadequate Installation.Data Is Being Evaluated from Walkdowns of Other Vital Equipment Cable Tray Areas
05000336/LER-1996-003-01, :on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys1998-09-0404 September 1998
- on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys
05000336/LER-1998-016-01, :on 980708,inadequate Adminstrative Controls on Safety Injection Valve Were Noted.Caused by Failure in 1976 to Understand & Implement Requirement to Close Valve 2-SI-459 within Time Limit.Revised Appropriate Procedures1998-08-0707 August 1998
- on 980708,inadequate Adminstrative Controls on Safety Injection Valve Were Noted.Caused by Failure in 1976 to Understand & Implement Requirement to Close Valve 2-SI-459 within Time Limit.Revised Appropriate Procedures
05000336/LER-1998-015-01, :on 980504,channel Functional Testing of Digital Radiation Monitors Did Not Comply W/Ts.Caused by Inadequate Evaluation of Adequacy of Test Methodology. Procedure Changes Will Be Implemented1998-07-30030 July 1998
- on 980504,channel Functional Testing of Digital Radiation Monitors Did Not Comply W/Ts.Caused by Inadequate Evaluation of Adequacy of Test Methodology. Procedure Changes Will Be Implemented
05000423/LER-1996-004-01, :on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment1998-07-30030 July 1998
- on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment
05000423/LER-1998-032, :on 980618,missed Fuel Handling Crane Limit Switch Surveillance Test Performance Was Noted.Caused by Human Error.Worker Was Coached on Need to Validate Performance of Surveillances Called Out in OPS Forms1998-07-17017 July 1998
- on 980618,missed Fuel Handling Crane Limit Switch Surveillance Test Performance Was Noted.Caused by Human Error.Worker Was Coached on Need to Validate Performance of Surveillances Called Out in OPS Forms
05000423/LER-1998-034, :on 980614,manual Reactor Trip Initiated in Response to Malfunction of Control Rod Group Demand Position Indication Counters.Caused by Human Error.Control Rod Group Step Counters Modified to Correct Condition1998-07-13013 July 1998
- on 980614,manual Reactor Trip Initiated in Response to Malfunction of Control Rod Group Demand Position Indication Counters.Caused by Human Error.Control Rod Group Step Counters Modified to Correct Condition
05000423/LER-1998-035, :on 980612,service Water Pump Cubicle Temperature Could Exceed Design Basis,Was Determined.Caused by Inadequate Design Control Process During Initial Plant Design.Reviewed & Revised Design Basis Calculations1998-07-13013 July 1998
- on 980612,service Water Pump Cubicle Temperature Could Exceed Design Basis,Was Determined.Caused by Inadequate Design Control Process During Initial Plant Design.Reviewed & Revised Design Basis Calculations
05000423/LER-1998-033, :on 980610,manual ESF Actuation of Motor Driven Auxiliary FW Pumps Was Noted.Caused by Trip of Motor Driven SG FW Pump.Motor Driven FW Pump Impeller Was Replaced1998-07-10010 July 1998
- on 980610,manual ESF Actuation of Motor Driven Auxiliary FW Pumps Was Noted.Caused by Trip of Motor Driven SG FW Pump.Motor Driven FW Pump Impeller Was Replaced
05000423/LER-1998-027, :on 980416,determined That Unmonitored Flowpaths Existed for Diesel Fuel Oil Transfer Pumps During IST Testing.Caused by Program & Process Re Deficiencies. Review of Past Surveillance Results Conducted1998-06-26026 June 1998
- on 980416,determined That Unmonitored Flowpaths Existed for Diesel Fuel Oil Transfer Pumps During IST Testing.Caused by Program & Process Re Deficiencies. Review of Past Surveillance Results Conducted
05000336/LER-1998-013-01, :on 980526,shutdown Cooling Sys Was Over Pressurized by Inadvertent Hpsip Start.Caused by Inadequate Evaluation in Original Plant Design.Appropriate Actions Were Taken to Ensure Sys Complies W/Design & Licensing Basis1998-06-25025 June 1998
- on 980526,shutdown Cooling Sys Was Over Pressurized by Inadvertent Hpsip Start.Caused by Inadequate Evaluation in Original Plant Design.Appropriate Actions Were Taken to Ensure Sys Complies W/Design & Licensing Basis
05000336/LER-1998-011-01, :on 980519,determined That Valves Had Been Closing Completely Under No Flow Conditions.Caused by Improper Valve Setup & Failure to Verify Adequate Valve Closure.Valves Disassembled1998-06-18018 June 1998
- on 980519,determined That Valves Had Been Closing Completely Under No Flow Conditions.Caused by Improper Valve Setup & Failure to Verify Adequate Valve Closure.Valves Disassembled
05000336/LER-1998-010-01, :on 980508,discovered That Encl Bldg Surveillance Procedure Did Not Adequately Verify Leak Integrity of Encl B.Caused by Inadequate Evaluation of Phenomenon Described in NRC Info Notice.Amend Implemented1998-06-0505 June 1998
- on 980508,discovered That Encl Bldg Surveillance Procedure Did Not Adequately Verify Leak Integrity of Encl B.Caused by Inadequate Evaluation of Phenomenon Described in NRC Info Notice.Amend Implemented
05000336/LER-1998-009-01, :on 980501,LBLOCA Analysis Indicates Peak Clad Temp Could Exceed 2200 Degrees F.Caused by Failure to Identify Excessive Variability.Reanalyzed LBLOCA Using Current & Corrected Evaluation Models1998-05-28028 May 1998
- on 980501,LBLOCA Analysis Indicates Peak Clad Temp Could Exceed 2200 Degrees F.Caused by Failure to Identify Excessive Variability.Reanalyzed LBLOCA Using Current & Corrected Evaluation Models
05000336/LER-1998-008-01, :on 980423,TS Violations Were Noted.Caused by Failure to Achieve Compliance to TS Requirements.Revised Appropriate Surveillance Procedures1998-05-26026 May 1998
- on 980423,TS Violations Were Noted.Caused by Failure to Achieve Compliance to TS Requirements.Revised Appropriate Surveillance Procedures
05000423/LER-1998-026, :on 980424,noted That Analyzed SGTR Thyroid Dose Contained non-conservative Assumption.Caused by Inadequate Review by Individual.Will Revise SGTR Offsite Dose Analysis to Reflect Mass Release Analysis1998-05-24024 May 1998
- on 980424,noted That Analyzed SGTR Thyroid Dose Contained non-conservative Assumption.Caused by Inadequate Review by Individual.Will Revise SGTR Offsite Dose Analysis to Reflect Mass Release Analysis
05000245/LER-1996-023-01, :on 960306,movement of New Fuel Assemblies Over Spent Fuel Pool Resulted in Condition Outside of Design Basis of Plant.Caused by Personnel Error.New Fuel Elevator Tagged Out & Deenergized to Prevent Use1998-05-12012 May 1998
- on 960306,movement of New Fuel Assemblies Over Spent Fuel Pool Resulted in Condition Outside of Design Basis of Plant.Caused by Personnel Error.New Fuel Elevator Tagged Out & Deenergized to Prevent Use
05000336/LER-1998-007-02, :on 980408,reanalysis of Ms Line Break Indicated Possible Fuel Failures.Cause Is Under Investigation.Siemens Analysis Will Be Completed Prior to Entering Mode 4 from Current Outage1998-05-0808 May 1998
- on 980408,reanalysis of Ms Line Break Indicated Possible Fuel Failures.Cause Is Under Investigation.Siemens Analysis Will Be Completed Prior to Entering Mode 4 from Current Outage
05000245/LER-1998-005-02, :on 980330,loss of S1 & S2 Power Supply Were Noted Due to Single Failure.Caused by Inadequate Design & Indequate Mod Review.Abt & Breaker Configuration for MCC EF3 & MCC FE3 Will Be Evaluated1998-04-29029 April 1998
- on 980330,loss of S1 & S2 Power Supply Were Noted Due to Single Failure.Caused by Inadequate Design & Indequate Mod Review.Abt & Breaker Configuration for MCC EF3 & MCC FE3 Will Be Evaluated
05000336/LER-1998-006-01, :on 980327,reactor Bldg Closed Cooling Water Sys Outside Design Upon Loss of Svc Water Occurred.Caused by Inadequate Consideration of All Postulated Single Failure Events.Procedures Will Be Implemented1998-04-24024 April 1998
- on 980327,reactor Bldg Closed Cooling Water Sys Outside Design Upon Loss of Svc Water Occurred.Caused by Inadequate Consideration of All Postulated Single Failure Events.Procedures Will Be Implemented
05000423/LER-1998-021, :on 980318,discovered That Several Manual Valves & Check Valve Tests Were Not Included in IST Program. Caused by Lack of Clear Documentation.Satisfactorily Tested & Included Reported Valves in IST Program1998-04-17017 April 1998
- on 980318,discovered That Several Manual Valves & Check Valve Tests Were Not Included in IST Program. Caused by Lack of Clear Documentation.Satisfactorily Tested & Included Reported Valves in IST Program
05000423/LER-1998-020, :on 980320,identified That Daily Channel Check of Radioactive Liquid Effluent Waste Neutralization Sump Monitor Had Not Been Performed.Caused by Poorly Written Procedure.Revised Implementation Documents1998-04-13013 April 1998
- on 980320,identified That Daily Channel Check of Radioactive Liquid Effluent Waste Neutralization Sump Monitor Had Not Been Performed.Caused by Poorly Written Procedure.Revised Implementation Documents
05000423/LER-1998-019, :on 980313,documented Max Required Accident Condition Flow Through Check Valves within Inservice Test Program Versus Results of Surveillance Testing.Cauesd by Program & Process Related Deficiencies.Procedures Revised1998-04-13013 April 1998
- on 980313,documented Max Required Accident Condition Flow Through Check Valves within Inservice Test Program Versus Results of Surveillance Testing.Cauesd by Program & Process Related Deficiencies.Procedures Revised
05000336/LER-1998-004-02, :on 980316,auxiliary Feedwater Pump Performance Was Degraded.Cause of Condition Is Unknown.Pump Will Be Returned to Operable Status Prior to Mode 3 from Current Outage1998-04-0909 April 1998
- on 980316,auxiliary Feedwater Pump Performance Was Degraded.Cause of Condition Is Unknown.Pump Will Be Returned to Operable Status Prior to Mode 3 from Current Outage
05000336/LER-1998-005-01, :on 980318,high Energy Line Break Deficiencies for Piping Inside Containment Was Discovered.Caused by Inadequate Consideration of HELB Requirements in Original Facility Design.Engineering Study Will Be Completed1998-04-0909 April 1998
- on 980318,high Energy Line Break Deficiencies for Piping Inside Containment Was Discovered.Caused by Inadequate Consideration of HELB Requirements in Original Facility Design.Engineering Study Will Be Completed
05000245/LER-1998-004-01, :on 980311,failure to Recognize Rod Block Monitor Inoperable Occurred.Caused by Personnel Error. Procedures Will Be Revised to Require & Document Monitoring of Local Power Range Monitor1998-04-0808 April 1998
- on 980311,failure to Recognize Rod Block Monitor Inoperable Occurred.Caused by Personnel Error. Procedures Will Be Revised to Require & Document Monitoring of Local Power Range Monitor
05000336/LER-1998-003-02, :on 980113,inadequate Evaluation Between Reactor Internals & Rv Occurred.Caused by Inadequate Design Review.Appropriate Structural Analyses Revised1998-04-0303 April 1998
- on 980113,inadequate Evaluation Between Reactor Internals & Rv Occurred.Caused by Inadequate Design Review.Appropriate Structural Analyses Revised
05000423/LER-1998-018, :on 980302,TS LCO Action Not Completed within Specified Time Limit,Was Identified.Caused by Inadequate Administrative Controls.Written Expectations Re Conservative Philosophy When Scheduling or Performing LCO Surveillance1998-04-0101 April 1998
- on 980302,TS LCO Action Not Completed within Specified Time Limit,Was Identified.Caused by Inadequate Administrative Controls.Written Expectations Re Conservative Philosophy When Scheduling or Performing LCO Surveillance
05000423/LER-1998-017, :on 980227,3SIL*V15 Testing Was Contrary to TS 4.0.5 Requirements.Caused by Program & Process Deficiencies. Submittal of Relief Request to Allow Extension of Disassembly & Insp Interval for 3SIL*V15 Was Submitted1998-03-27027 March 1998
- on 980227,3SIL*V15 Testing Was Contrary to TS 4.0.5 Requirements.Caused by Program & Process Deficiencies. Submittal of Relief Request to Allow Extension of Disassembly & Insp Interval for 3SIL*V15 Was Submitted
05000423/LER-1998-016, :on 980223,potential for Air Binding Boric Acid Transfer Pumps Occurred Due to Air Accumulation in Sys During Batching Operations from Boric Acid Batching Tank. Procedure Changes Will Be Completed1998-03-25025 March 1998
- on 980223,potential for Air Binding Boric Acid Transfer Pumps Occurred Due to Air Accumulation in Sys During Batching Operations from Boric Acid Batching Tank. Procedure Changes Will Be Completed
05000423/LER-1998-014, :on 980220,failure to Provide Weepholes in Conduits & Junction Boxes Was Identified.Caused by Inadequate Review & Process Control.Conducted Walkdowns & Provided Weepholes to 227 Individual Components1998-03-23023 March 1998
- on 980220,failure to Provide Weepholes in Conduits & Junction Boxes Was Identified.Caused by Inadequate Review & Process Control.Conducted Walkdowns & Provided Weepholes to 227 Individual Components
05000423/LER-1998-013, :on 980219,determined That TS Required Sampling During Mode 5 Had Not Been Completed for SG Drain Down Due to Less than Adequate Communications Between Operations & Chemistry.Reinforced Applicability of TS Requirements1998-03-20020 March 1998
- on 980219,determined That TS Required Sampling During Mode 5 Had Not Been Completed for SG Drain Down Due to Less than Adequate Communications Between Operations & Chemistry.Reinforced Applicability of TS Requirements