Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000010/LER-1997-001-06, :on 970210,120 Volt Circuit Breaker Supplying Alternate Iodine & Particulate Sampling Sys Tripped.Caused by Mgt Deficiency.Disconnected Auxiliary Loads,Restricted Use of Outlets & Verified Continued Sys Operation1997-03-12012 March 1997
- on 970210,120 Volt Circuit Breaker Supplying Alternate Iodine & Particulate Sampling Sys Tripped.Caused by Mgt Deficiency.Disconnected Auxiliary Loads,Restricted Use of Outlets & Verified Continued Sys Operation
05000237/LER-1996-003-01, :on 960219,EP DGA-12 Failed to Provide Cro Action to Allow CR Air Filtration Unit to Operate as required.DGA-12 Revised to Give Guidance on Restoration of CR HVAC in Pressurization Mode1996-03-14014 March 1996
- on 960219,EP DGA-12 Failed to Provide Cro Action to Allow CR Air Filtration Unit to Operate as required.DGA-12 Revised to Give Guidance on Restoration of CR HVAC in Pressurization Mode
05000249/LER-1992-004-02, :on 920122,calculations Indicated Min Required 4 Kv Safety Bus Voltages for Buses 33-1 & 34-1 to Be 3832 Volts & 3792 Volts,Respectively.Caused by Inadequate Design Control.Mods Designed & Installed1992-02-21021 February 1992
- on 920122,calculations Indicated Min Required 4 Kv Safety Bus Voltages for Buses 33-1 & 34-1 to Be 3832 Volts & 3792 Volts,Respectively.Caused by Inadequate Design Control.Mods Designed & Installed
05000237/LER-1990-007-09, :on 900802,unplanned Primary Containment Group V Isolation Occurred.Cause Not Identified.Relay Circuitry & Sys Parameters Investigated Prior to Resetting Isolation Signal & Visual Observation Made1990-08-28028 August 1990
- on 900802,unplanned Primary Containment Group V Isolation Occurred.Cause Not Identified.Relay Circuitry & Sys Parameters Investigated Prior to Resetting Isolation Signal & Visual Observation Made
05000237/LER-1989-032, :on 891210,as-left Type B & C Local Leak Rate Test Data Exceeded Tech Spec Limit of 488.452 Std Cubic Ft/H.Caused by Degradation of Telephone & Electrical Conduit Penetration Seal.Conduit Cut & Capped1989-12-29029 December 1989
- on 891210,as-left Type B & C Local Leak Rate Test Data Exceeded Tech Spec Limit of 488.452 Std Cubic Ft/H.Caused by Degradation of Telephone & Electrical Conduit Penetration Seal.Conduit Cut & Capped
05000237/LER-1989-001-05, :on 890121,unanticipated Reactor Scram & Group II Primary Containment Isolation Occurred Due to Loss of Reactor Protection Sys Motor Generator Sets.Caused by Procedural Deficiency.Procedure Reviewed1989-02-21021 February 1989
- on 890121,unanticipated Reactor Scram & Group II Primary Containment Isolation Occurred Due to Loss of Reactor Protection Sys Motor Generator Sets.Caused by Procedural Deficiency.Procedure Reviewed
05000249/LER-1988-009-03, :on 880505,Groups II & III Primary Containment Isolation Occurred During Shutdown for Scheduled Refueling Outage.Caused by Mgt Deficiency for Failure to Implement Corrective Actions from Previous Event1988-06-0303 June 1988
- on 880505,Groups II & III Primary Containment Isolation Occurred During Shutdown for Scheduled Refueling Outage.Caused by Mgt Deficiency for Failure to Implement Corrective Actions from Previous Event
05000237/LER-1988-007-06, :on 880504,discovered That CRD Scram Testing Surveillance Interval Exceeded.Caused by Scram Testing Procedure Deficiency.Strip Chart Event Recorder Wired, Utilizing Wire plug-in Jacks1988-06-0101 June 1988
- on 880504,discovered That CRD Scram Testing Surveillance Interval Exceeded.Caused by Scram Testing Procedure Deficiency.Strip Chart Event Recorder Wired, Utilizing Wire plug-in Jacks
05000237/LER-1988-006-07, :on 880429,primary Nitrogen Inerting Makeup Sys Line Kinked & Cracked.Caused by Personnel Error & Rigging Procedure Deficiency.Rigging Procedure Improvement Initiated & Addl Rigging Operations Training Planned1988-05-25025 May 1988
- on 880429,primary Nitrogen Inerting Makeup Sys Line Kinked & Cracked.Caused by Personnel Error & Rigging Procedure Deficiency.Rigging Procedure Improvement Initiated & Addl Rigging Operations Training Planned
05000237/LER-1988-008-04, :on 880506,reactor Bldg Ventilation Sys Automatically Tripped & Standby Gas Treatment Train Auto Started.Caused by Error in Chemistry Procedure 2000-5. Radiation Source Removed from Monitor1988-05-25025 May 1988
- on 880506,reactor Bldg Ventilation Sys Automatically Tripped & Standby Gas Treatment Train Auto Started.Caused by Error in Chemistry Procedure 2000-5. Radiation Source Removed from Monitor
05000237/LER-1988-005-06, :on 880426,reactor Bldg Ventilation Sys (RBVS) Tripped,Initiating Standby Gas Treatment a Sys Train.Caused by Spurious Instantaneous Spike on Unit 2 Rbvs.Calibr Check of Unit 2 RBVS Performed Satisfactorily1988-05-17017 May 1988
- on 880426,reactor Bldg Ventilation Sys (RBVS) Tripped,Initiating Standby Gas Treatment a Sys Train.Caused by Spurious Instantaneous Spike on Unit 2 Rbvs.Calibr Check of Unit 2 RBVS Performed Satisfactorily
05000249/LER-1988-010-01, :on 880424,main Steam Safety Valve 3-203-4D Opened at Pressure in Excess of Tech Spec 4.6.E Required Setpoint.Caused by Setpoint Drift.Valve Overhauling,Setting & Retesting Prior to Installation Planned1988-05-13013 May 1988
- on 880424,main Steam Safety Valve 3-203-4D Opened at Pressure in Excess of Tech Spec 4.6.E Required Setpoint.Caused by Setpoint Drift.Valve Overhauling,Setting & Retesting Prior to Installation Planned
05000249/LER-1988-011, :on 880412,Group II Primary Containment Isolation Occurred.Caused by Procedural Inadequacy.Power Restored to Monitors & Isolation Reset.Procedural Change Being Investigated1988-05-10010 May 1988
- on 880412,Group II Primary Containment Isolation Occurred.Caused by Procedural Inadequacy.Power Restored to Monitors & Isolation Reset.Procedural Change Being Investigated
05000249/LER-1988-007-04, :on 880413,standby Liquid Control Relief Valves Failed to Open During Performance.Caused by Blockage as Result of Sodium Pentaborate Solution.Procedure Will Be Revised to Indicate Testing of Relief Valves1988-05-0606 May 1988
- on 880413,standby Liquid Control Relief Valves Failed to Open During Performance.Caused by Blockage as Result of Sodium Pentaborate Solution.Procedure Will Be Revised to Indicate Testing of Relief Valves
05000249/LER-1988-004-07, :on 880404,atmosphere Containment & Dilution Purge Check Valve Leaked Exceeding Tech Spec Limit.Cause of Leakage Undetermined.Cause Will Be Determined & Valve Will Be Repaired & Retested1988-04-28028 April 1988
- on 880404,atmosphere Containment & Dilution Purge Check Valve Leaked Exceeding Tech Spec Limit.Cause of Leakage Undetermined.Cause Will Be Determined & Valve Will Be Repaired & Retested
05000237/LER-1988-001, :on 880329,diesel Generator Air Start Piping (Dgasp) Exceeded Code Stress Analysis Allowables Specified in Fsar.Caused by Original Design Deficiency.Mod of Dgasp on Unit 2 & Unit 3 Planned1988-04-25025 April 1988
- on 880329,diesel Generator Air Start Piping (Dgasp) Exceeded Code Stress Analysis Allowables Specified in Fsar.Caused by Original Design Deficiency.Mod of Dgasp on Unit 2 & Unit 3 Planned
05000237/LER-1988-001-12, :on 880329,diesel Generator Air Start Piping Found Outside FSAR Design Criteria.Caused by Original Design Deficiency.Mods Initiated to Modify Piping Sys & Procedure DAP 5-1, Plant Mod Program, Revised1988-04-25025 April 1988
- on 880329,diesel Generator Air Start Piping Found Outside FSAR Design Criteria.Caused by Original Design Deficiency.Mods Initiated to Modify Piping Sys & Procedure DAP 5-1, Plant Mod Program, Revised
05000249/LER-1988-005-03, :on 880326,HPCI Sys Made Inoperable to Facilitate Preplanned Preventive Maint Testing.Caused by Mgt Decision to Perform Preventive Maint Testing of HPCI Turbine Overspeed Trip Sys.Hpci Tripped on 5,015 Rpm1988-04-18018 April 1988
- on 880326,HPCI Sys Made Inoperable to Facilitate Preplanned Preventive Maint Testing.Caused by Mgt Decision to Perform Preventive Maint Testing of HPCI Turbine Overspeed Trip Sys.Hpci Tripped on 5,015 Rpm
05000249/LER-1988-003-06, :on 880323,flued Head Anchor (FHA) Supports Found in Excess of FSAR Design Criteria.Caused by Design & Const Deficiencies.Repairs to FHA to Be Performed Under Mod M12-3-88-201988-04-18018 April 1988
- on 880323,flued Head Anchor (FHA) Supports Found in Excess of FSAR Design Criteria.Caused by Design & Const Deficiencies.Repairs to FHA to Be Performed Under Mod M12-3-88-20
05000237/LER-1988-004-02, :on 880221,inoperable CRD E-9 Found Electrically Armed Due to Personnel Error.Crd Disarmed & out-of-svc Card Hung on Hydraulic Control Unit.Event Discussed W/Personnel at Weekly Meeting1988-03-15015 March 1988
- on 880221,inoperable CRD E-9 Found Electrically Armed Due to Personnel Error.Crd Disarmed & out-of-svc Card Hung on Hydraulic Control Unit.Event Discussed W/Personnel at Weekly Meeting
05000237/LER-1988-002-04, :on 880201,identified Deficiency in Weekly APRM Surveillance Procedure Operational Surveillance,Aprm Rod Block & Scram Function Test.Caused by Procedural Deficiency. Procedure to Be Revised to Ensure Weekly Tests1988-02-29029 February 1988
- on 880201,identified Deficiency in Weekly APRM Surveillance Procedure Operational Surveillance,Aprm Rod Block & Scram Function Test.Caused by Procedural Deficiency. Procedure to Be Revised to Ensure Weekly Tests
05000249/LER-1988-002-01, :on 880113,emergency Diesel Generator Automatically Started W/No Initiation Conditions Indicated in Control Room.Caused by Mgt Deficiency Re Work Activity on Inservice Equipment.Station Policy Issued1988-02-0404 February 1988
- on 880113,emergency Diesel Generator Automatically Started W/No Initiation Conditions Indicated in Control Room.Caused by Mgt Deficiency Re Work Activity on Inservice Equipment.Station Policy Issued
05000249/LER-1988-001, :on 880105,discovered That 41 Individual Type B & C Local Leak Rate Tests Performed During Previous Refueling Outage Had Individual Testing Intervals Exceeding 24 Months.Review Conducted1988-01-29029 January 1988
- on 880105,discovered That 41 Individual Type B & C Local Leak Rate Tests Performed During Previous Refueling Outage Had Individual Testing Intervals Exceeding 24 Months.Review Conducted
05000237/LER-1987-010, :on 870317,discovered Embedment Plate for Support Located on Core Spray Sys a Piping Degraded.Six Addl Discrepancies Found During Review of Sys.Caused by Improper Hold Down Clamp Spacings.Repairs Completed1988-01-27027 January 1988
- on 870317,discovered Embedment Plate for Support Located on Core Spray Sys a Piping Degraded.Six Addl Discrepancies Found During Review of Sys.Caused by Improper Hold Down Clamp Spacings.Repairs Completed
05000237/LER-1987-035-02, :on 871219,while Responding to APRM 4 hi-hi Alarm,Operator Noted Number of Operable APRM Downscale Trips in Reactor Protection Sys Insufficient.Caused by Personnel Error.Procedure Changed & Operator Counseled1988-01-0808 January 1988
- on 871219,while Responding to APRM 4 hi-hi Alarm,Operator Noted Number of Operable APRM Downscale Trips in Reactor Protection Sys Insufficient.Caused by Personnel Error.Procedure Changed & Operator Counseled
05000249/LER-1983-002-01, /01T-0:on 830105,leakage from RWCU Test Tap Valve 3-1299-13 Occurred.Caused by Seat Damage of Valve.Valve Replaced During 1983 Refueling Outage1987-12-17017 December 1987 /01T-0:on 830105,leakage from RWCU Test Tap Valve 3-1299-13 Occurred.Caused by Seat Damage of Valve.Valve Replaced During 1983 Refueling Outage 05000237/LER-1982-058-03, /03L-1:on 821226,small Leak Found on RWCU Line 2-1201B Between 2-1201-135B & 2-1201-98B Valves.Caused by IGSCC at heat-affected Zone Near Weld.Degraded Pipe Section Replaced Per Work Package D247801987-12-15015 December 1987 /03L-1:on 821226,small Leak Found on RWCU Line 2-1201B Between 2-1201-135B & 2-1201-98B Valves.Caused by IGSCC at heat-affected Zone Near Weld.Degraded Pipe Section Replaced Per Work Package D24780 05000249/LER-1986-018-01, :on 861014,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented1987-12-11011 December 1987
- on 861014,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented
05000249/LER-1986-020, :on 861113,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented1987-12-11011 December 1987
- on 861113,spurious Group V Containment Isolation Occurred.Caused by Differential Pressure Spikes &/Or Noise Generated by Annubar Flow Instrument.Mod to Isolation Circuitry Implemented
05000249/LER-1987-005, :on 870316,primary Containment Drywell Structural Steel Failed FSAR Design Requirements.Caused by Inadequate Verification of as-built Condition W/Design Prints During Const.Repair & Insp Planned1987-12-0909 December 1987
- on 870316,primary Containment Drywell Structural Steel Failed FSAR Design Requirements.Caused by Inadequate Verification of as-built Condition W/Design Prints During Const.Repair & Insp Planned
05000237/LER-1987-033-02, :on 871110,reactor Bldg Ventilation Sys Sample Holder Contained No Particulate Sample Filter.Caused by Personnel Error.New Procedure Written & Sample Filter Replaced1987-11-30030 November 1987
- on 871110,reactor Bldg Ventilation Sys Sample Holder Contained No Particulate Sample Filter.Caused by Personnel Error.New Procedure Written & Sample Filter Replaced
05000237/LER-1987-030-02, :on 871013 & 16,main Steam Valve Setpoints Found Outside Tech Spec 4.6.E Limits.Caused by Mishandling of Valves During Transport & Setpoint Drift.Valves Will Be Overhauled,Retested,Reset & Procedure Improved1987-11-13013 November 1987
- on 871013 & 16,main Steam Valve Setpoints Found Outside Tech Spec 4.6.E Limits.Caused by Mishandling of Valves During Transport & Setpoint Drift.Valves Will Be Overhauled,Retested,Reset & Procedure Improved
05000237/LER-1987-010-01, :on 870317,core Spray Sys a Analytical Piping Stresses Exceeded FSAR Design Requirements.Caused by Design & Const Errors.Sys Analysis Model Revised to Address as-found Condition1987-11-12012 November 1987
- on 870317,core Spray Sys a Analytical Piping Stresses Exceeded FSAR Design Requirements.Caused by Design & Const Errors.Sys Analysis Model Revised to Address as-found Condition
05000237/LER-1987-019, :on 860811,reactor Scram Occurred from Main Turbine Trip on High Water Level.Caused by Personnel Error. Event Will Be Reviewed W/All Operators & Action Item Record 12-87-10 Issued to BWR Engineering Dept1987-11-0707 November 1987
- on 860811,reactor Scram Occurred from Main Turbine Trip on High Water Level.Caused by Personnel Error. Event Will Be Reviewed W/All Operators & Action Item Record 12-87-10 Issued to BWR Engineering Dept
05000237/LER-1987-001-02, :on 870102,ultrasonic Testing Showed Through Wall Indications on Weld PD5-D20.On 870121.circumferential Indication Through Wall of RWCU Sys 8 Weld 8-12 Discovered. Caused by Igscc.Evaluation Performed & Welds Repaired1987-11-0707 November 1987
- on 870102,ultrasonic Testing Showed Through Wall Indications on Weld PD5-D20.On 870121.circumferential Indication Through Wall of RWCU Sys 8 Weld 8-12 Discovered. Caused by Igscc.Evaluation Performed & Welds Repaired
05000237/LER-1987-032-02, :on 871020,primary Containment Group I Isolation & Reactor Scram Occurred.Caused by Vibration of Main Steam Line Low Pressure Switch.Isolators Installed to Make Switches Less Susceptible to Vibration1987-11-0505 November 1987
- on 871020,primary Containment Group I Isolation & Reactor Scram Occurred.Caused by Vibration of Main Steam Line Low Pressure Switch.Isolators Installed to Make Switches Less Susceptible to Vibration
05000237/LER-1987-034-01, :on 871016,discovered That Nonconservative Core Thermal Power Calculation Due to Inadequate Calibr Procedure.Rosemount Feedwater Flow Transmitters Recalibr & Listed Procedures to Be Revised1987-11-0404 November 1987
- on 871016,discovered That Nonconservative Core Thermal Power Calculation Due to Inadequate Calibr Procedure.Rosemount Feedwater Flow Transmitters Recalibr & Listed Procedures to Be Revised
05000237/LER-1987-022-02, :on 870818,APRM 4 Generated Spurious hi-hi Signal Which Tripped Reactor Protection Sys Channel.Caused by Administrative Deficiency.Operating Order & Procedure Changes Alerting Operators Issued1987-09-15015 September 1987
- on 870818,APRM 4 Generated Spurious hi-hi Signal Which Tripped Reactor Protection Sys Channel.Caused by Administrative Deficiency.Operating Order & Procedure Changes Alerting Operators Issued
05000249/LER-1984-019-02, :on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design1987-08-0303 August 1987
- on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design
05000249/LER-1987-008, :on 870321,reactor Scrammed on Low Reactor Water Level.Caused by Procedural Inadequacy in Conjunction W/Component Failure.Procedure Revised to Add Provision for Opening Feedwater Pump Discharge Valves1987-04-29029 April 1987
- on 870321,reactor Scrammed on Low Reactor Water Level.Caused by Procedural Inadequacy in Conjunction W/Component Failure.Procedure Revised to Add Provision for Opening Feedwater Pump Discharge Valves
05000237/LER-1987-006-02, :on 870228,during Refueling,Reactor Scram & Group II Isolation Occurred.Caused by Trip at Bus 28 of Main Feed Breaker of Motor Control Ctr (MCC) 28-2.Reactor Protection Sys Bus 2B Transferred to MCC 25-21987-03-30030 March 1987
- on 870228,during Refueling,Reactor Scram & Group II Isolation Occurred.Caused by Trip at Bus 28 of Main Feed Breaker of Motor Control Ctr (MCC) 28-2.Reactor Protection Sys Bus 2B Transferred to MCC 25-2
05000237/LER-1987-007-02, :on 870227,drywell Structural Steel Radial Beam Discovered Outside Design Requirements.Caused by Reinstallation Deficiency.Beam Repair Completed on 870314, Per Engineering Change Notice D875-091987-03-25025 March 1987
- on 870227,drywell Structural Steel Radial Beam Discovered Outside Design Requirements.Caused by Reinstallation Deficiency.Beam Repair Completed on 870314, Per Engineering Change Notice D875-09
05000249/LER-1987-002-09, :on 870225,while Unit Operating at 87% Power, HPCI Sys Discovered Inoperable.Caused by Oil Pressure Regulation Valve Failure.Similar Event Occurred on 870313. Limits of PS4 Reset to 60 Psig Increasing1987-03-25025 March 1987
- on 870225,while Unit Operating at 87% Power, HPCI Sys Discovered Inoperable.Caused by Oil Pressure Regulation Valve Failure.Similar Event Occurred on 870313. Limits of PS4 Reset to 60 Psig Increasing
05000249/LER-1987-003-06, :on 870227,shutdown Cooling HX Outlet Temp Found Greater than 212 F.Caused by Operator Failure to Adequately Monitor Reactor Water Temp on Proper Instrumentation.Water Temp Reduced1987-03-24024 March 1987
- on 870227,shutdown Cooling HX Outlet Temp Found Greater than 212 F.Caused by Operator Failure to Adequately Monitor Reactor Water Temp on Proper Instrumentation.Water Temp Reduced
05000237/LER-1987-005-02, :on 870218,w/unit Shut Down for Refueling Outage,Snubbers 1301,1302 & 1303 Failed to Activate or Bleed within Allowable Ranges.Caused by Upgraded Test Acceptance Criteria.Two Mechanical Snubbers Installed1987-03-21021 March 1987
- on 870218,w/unit Shut Down for Refueling Outage,Snubbers 1301,1302 & 1303 Failed to Activate or Bleed within Allowable Ranges.Caused by Upgraded Test Acceptance Criteria.Two Mechanical Snubbers Installed
05000249/LER-1987-001-09, :on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established1987-03-0303 March 1987
- on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established
05000237/LER-1987-003, :on 870108,primary Containment Drywell Structural Steel Did Not Meet FSAR Design Requirements Due to Inadequate Connections Between Radial & Tangential Beams. Caused by Inadequate Confirmation of Const1987-02-0606 February 1987
- on 870108,primary Containment Drywell Structural Steel Did Not Meet FSAR Design Requirements Due to Inadequate Connections Between Radial & Tangential Beams. Caused by Inadequate Confirmation of Const
05000237/LER-1987-003-01, :on 870108,found Primary Containment Drywell Structural Steel Not Meeting FSAR Design Requirements.Caused by Inadequate Confirmation of Original Const & as-built Configuration.Repair Program Developed1987-02-0606 February 1987
- on 870108,found Primary Containment Drywell Structural Steel Not Meeting FSAR Design Requirements.Caused by Inadequate Confirmation of Original Const & as-built Configuration.Repair Program Developed
05000249/LER-1986-026-03, :on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development1987-02-0505 February 1987
- on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development
05000237/LER-1987-004-01, :on 870108,primary Containment Type B & C Local Leak Rate Test Limit Exceeded Due to Excessive Leakage Through Isolation Valve.Valve Will Be Repaired & Retested Per Dts 1600-1 When Cause Determined1987-01-29029 January 1987
- on 870108,primary Containment Type B & C Local Leak Rate Test Limit Exceeded Due to Excessive Leakage Through Isolation Valve.Valve Will Be Repaired & Retested Per Dts 1600-1 When Cause Determined
1997-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17191B4751999-10-0101 October 1999 Safety Evaluation Supporting Amends 175 & 171 to Licenses DPR-19 & DPR-25,respectively ML17191B4721999-10-0101 October 1999 Safety Evaluation Supporting Amends 174 & 170 to Licenses DPR-19 & DPR-25,respectively ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML17191B4591999-09-23023 September 1999 Safety Evaluation Supporting Amends 173 & 169 to Licenses DPR-19 & DPR-25,respectively ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML17191B4101999-07-27027 July 1999 Safety Evaluation Accepting Alternative to Licenses NPF-72, NPF-77,NPF-37,NPF-66,NPF-19,NPF-25,NPF-11,NPF-18,DPR-29 & DPR-30,respectively ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20207G3871999-06-0404 June 1999 Safety Evaluation Supporting Amend 168 to License DPR-25 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML17191B3541999-05-18018 May 1999 Safety Evaluation Concluding That Licensee Proposal to Reexamine Flaw According to Guidelines & Schedule of BWRVIP-41 Acceptable.Concludes That Licensee Leakage Evaluation Adequate ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML17191B3081999-04-0101 April 1999 Safety Evaluation of Topical Rept NPSR-0111,rev 1, BWR Transient Analysis Methods. Rept Acceptable for Inclusion in Licensing Submittals ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML17191B2811999-03-16016 March 1999 Safety Evaluation Supporting Amends 172,167,184,181,132 & 117 to Licenses DPR-19,DPR-25,DPR-29,DPR-30,NPF-11 & NPF-18, Respectively ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17191B2391999-02-16016 February 1999 Safety Evaluation Supporting Amends 171 & 166 to Licenses DPR-19 & DPR-25,respectively ML17191B2371999-02-0808 February 1999 Safety Evaluation Supporting Amends 170,165,183 & 180 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With ML17191A9011998-10-0101 October 1998 Safety Evaluation Concluding That Ceco Adequately Addressed Actions Requested in GL 95-07 Issued on 950817 ML20154N4131998-09-30030 September 1998 1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20154L3681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML17191A8891998-09-23023 September 1998 Safety Evaluation Accepting Continued Operation for Plant, Unit 3 Without Repair,For Four Fuel Cycles ML20153C5061998-09-21021 September 1998 SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1 ML20151Y2711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML17191A8831998-08-27027 August 1998 Safety Evaluation Accepting Purge & Vent Strategy for Primary Containment Hydrogen Control at Plant ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1341998-08-0707 August 1998 Safety Evaluation Supporting Amend 163 to License DPR-25 ML17191A8231998-08-0505 August 1998 SER Related to Reactor Pressure Vessel Head Stud Flaw Tolerance Evaluation for Dresden Nuclear Power Station,Unit 2 ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20248M3021998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F3391998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 1999-09-30
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