Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000254/LER-1999-004-03, :on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-021999-10-12012 October 1999
- on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-02
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure1999-10-0707 October 1999
- on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
05000265/LER-1999-002-04, :on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 9907151999-06-25025 June 1999
- on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 990715
05000254/LER-1999-004-02, :on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised1999-06-18018 June 1999
- on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised
05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance1999-05-12012 May 1999
- on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
05000254/LER-1998-001-01, :on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation1998-10-27027 October 1998
- on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation
05000265/LER-1998-006-04, :on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-061998-10-15015 October 1998
- on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-06
05000265/LER-1998-005-07, :on 980729,HPCI Subsystem Turning Gear Failed to Engage Automatically Rendering HPCI Subsystem Inoperable. Caused by Failed Limit Switch in Tgr Logic.Limit Switch & Pressure Switch Were Replaced1998-08-28028 August 1998
- on 980729,HPCI Subsystem Turning Gear Failed to Engage Automatically Rendering HPCI Subsystem Inoperable. Caused by Failed Limit Switch in Tgr Logic.Limit Switch & Pressure Switch Were Replaced
05000254/LER-1998-011-02, :on 980716,unqualified Circuit Card Was Installed in SD Instrument Vol Level Transmitter,Rendering It Inoperable.Caused by Personnel Error.Reviewed Event with Instrument Maint,Sys Engineering & Procurement Engineering1998-08-12012 August 1998
- on 980716,unqualified Circuit Card Was Installed in SD Instrument Vol Level Transmitter,Rendering It Inoperable.Caused by Personnel Error.Reviewed Event with Instrument Maint,Sys Engineering & Procurement Engineering
05000265/LER-1998-003-06, :on 980628,main Generator Trip & Subsequent Reactor Scram Occurred Due to Loose Electrical Connection in Current Transformer.Caused by Vibrations.Stabilized Unit 2 by Placing Unit in Hot Shutdown1998-07-27027 July 1998
- on 980628,main Generator Trip & Subsequent Reactor Scram Occurred Due to Loose Electrical Connection in Current Transformer.Caused by Vibrations.Stabilized Unit 2 by Placing Unit in Hot Shutdown
05000265/LER-1998-002-07, :on 970609,H Samples Were Not Collected IAW TS Sr.Caused by Misinterpretation of TS Requirements.Revised Procedure & Reviewed Other Comed Stations Implementation of TS to Identify & Resolve Any Discrepancies1998-06-24024 June 1998
- on 970609,H Samples Were Not Collected IAW TS Sr.Caused by Misinterpretation of TS Requirements.Revised Procedure & Reviewed Other Comed Stations Implementation of TS to Identify & Resolve Any Discrepancies
05000254/LER-1998-012-01, :on 980227,reactor Bottom Head Drain Line Developed Leak.Caused by Inadequate Work Practice During Original Construction.Replaced Leaking Section of Drain Line Under Design Change Package(Dcp 9800100)1998-05-29029 May 1998
- on 980227,reactor Bottom Head Drain Line Developed Leak.Caused by Inadequate Work Practice During Original Construction.Replaced Leaking Section of Drain Line Under Design Change Package(Dcp 9800100)
05000254/LER-1998-016, :on 980411,determined That TS Scram Discharge Volume Instruments Exceeded Setpoint.Caused by Insufficient Setpoint Margin.Revised Setpoints & Implemented Addl Margin to Account for Drift1998-05-0808 May 1998
- on 980411,determined That TS Scram Discharge Volume Instruments Exceeded Setpoint.Caused by Insufficient Setpoint Margin.Revised Setpoints & Implemented Addl Margin to Account for Drift
05000254/LER-1997-015-02, :on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test1998-04-10010 April 1998
- on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test
05000254/LER-1998-014, :on 980306,required ASME Section XI Code Examination for Feedwater Nozzles Were Not Conducted During Second Ten Year Interval.Caused by Weakness in Processes Existing at Time for Completion.Searches Were Completed1998-04-0505 April 1998
- on 980306,required ASME Section XI Code Examination for Feedwater Nozzles Were Not Conducted During Second Ten Year Interval.Caused by Weakness in Processes Existing at Time for Completion.Searches Were Completed
05000254/LER-1998-013, :on 980131,discovered Insufficient Clearance Between Core Spray Test Return Valve & Pressure Suppression Chamber.Caused by Inattention to Detail in Original Design. Removed Pad to Restore Adequate Clearance1998-03-30030 March 1998
- on 980131,discovered Insufficient Clearance Between Core Spray Test Return Valve & Pressure Suppression Chamber.Caused by Inattention to Detail in Original Design. Removed Pad to Restore Adequate Clearance
05000254/LER-1998-012, :on 980227,discovered Leak in Reactor Bottom Head Drain Line.Caused by Apparent Cracking of Piping Coupling Weld.Replaced Leaking Section of Reactor Vessel Drain Line1998-03-27027 March 1998
- on 980227,discovered Leak in Reactor Bottom Head Drain Line.Caused by Apparent Cracking of Piping Coupling Weld.Replaced Leaking Section of Reactor Vessel Drain Line
05000254/LER-1997-030, :on 971217,noted That Instrument Line Excess Flow Valves Testing Was Performed at Less than Nominal Reactor Pressure.Caused by Inadequate Procedures.Will Revise Implementing Procedure to Specify Pressure Requirements1998-03-27027 March 1998
- on 971217,noted That Instrument Line Excess Flow Valves Testing Was Performed at Less than Nominal Reactor Pressure.Caused by Inadequate Procedures.Will Revise Implementing Procedure to Specify Pressure Requirements
05000265/LER-1998-001-10, :on 971122,TS Surveillance for SRM Was Not Performed within Required Interval for Units 1 & 2 Due to Inadequate Identification of TS Requirement in Surveillance. Surveillance Was Performed for Units 1 & 2 on 9802221998-03-17017 March 1998
- on 971122,TS Surveillance for SRM Was Not Performed within Required Interval for Units 1 & 2 Due to Inadequate Identification of TS Requirement in Surveillance. Surveillance Was Performed for Units 1 & 2 on 980222
05000254/LER-1998-010, :on 980213,TS Surveillance Interval for Snubber Visual Insp Was Exceeded.Caused by Personnel Error.Completed TS Insps & Engineering Evaluations,Verification of Correct Insp Interval Dates & Personal Accountability Actions1998-03-16016 March 1998
- on 980213,TS Surveillance Interval for Snubber Visual Insp Was Exceeded.Caused by Personnel Error.Completed TS Insps & Engineering Evaluations,Verification of Correct Insp Interval Dates & Personal Accountability Actions
05000254/LER-1998-009, :on 980210,temp Switches Used to Perform Daily Verification Were Set Below Value Needed to Support Ts. Caused by Failure to Establish During Implementation of TS Program.Revised Procedures to Take Reading Once Per 24 H1998-03-12012 March 1998
- on 980210,temp Switches Used to Perform Daily Verification Were Set Below Value Needed to Support Ts. Caused by Failure to Establish During Implementation of TS Program.Revised Procedures to Take Reading Once Per 24 H
05000254/LER-1998-005, :on 980206,failure to Complete Visual Periodic Insp for Rc Sources Outside Primary Containment Was Noted. Caused by Ineffective Scheduling & Tracking of Sys Insp. Assigned Owner to Oversee Leak Reduction Program1998-03-0606 March 1998
- on 980206,failure to Complete Visual Periodic Insp for Rc Sources Outside Primary Containment Was Noted. Caused by Ineffective Scheduling & Tracking of Sys Insp. Assigned Owner to Oversee Leak Reduction Program
05000254/LER-1998-008, :on 980127,determined That RHR Shutdown Cooling Common Suction Header Was Inoperable.Caused by Mechanical Failure of Mechanical Shock Arrestor (Snubber).Replaced Snubber & Completed off-site Failure Analysis of Snubber1998-02-25025 February 1998
- on 980127,determined That RHR Shutdown Cooling Common Suction Header Was Inoperable.Caused by Mechanical Failure of Mechanical Shock Arrestor (Snubber).Replaced Snubber & Completed off-site Failure Analysis of Snubber
05000254/LER-1998-006, :on 980128,RB Post LOCA Temperatures Are Higher than Values Used for Environ Qualification of Electrical Equipment Due to Unvalidated Engineering Judgment.Cause Undetermined.Preliminary Calculations Completed1998-02-24024 February 1998
- on 980128,RB Post LOCA Temperatures Are Higher than Values Used for Environ Qualification of Electrical Equipment Due to Unvalidated Engineering Judgment.Cause Undetermined.Preliminary Calculations Completed
05000254/LER-1997-030-01, :on 971223,instrument Line EFCV Testing Performed at Less than Nominal Rp.Caused by Inadequate Procedures.Appropriate Corrective Actions Will Be Identified in Supplemental Rept to Be Submitted Later1998-01-21021 January 1998
- on 971223,instrument Line EFCV Testing Performed at Less than Nominal Rp.Caused by Inadequate Procedures.Appropriate Corrective Actions Will Be Identified in Supplemental Rept to Be Submitted Later
05000254/LER-1994-002-03, :on 940104,B CR HVAC Declared Inoperable. Caused by Failure in Contactor Which Resulted from Cumulative Cycling of Compressor.Contactor Replaced1998-01-19019 January 1998
- on 940104,B CR HVAC Declared Inoperable. Caused by Failure in Contactor Which Resulted from Cumulative Cycling of Compressor.Contactor Replaced
05000254/LER-1997-027-01, :on 971218,EDGs Were Simultaneously Inoperable While Unit 1 Was at Power Due to Time Delay Relay 2 Failing to Meet Acceptance Criteria.Unit 1/2 EDG TD2 Relay Was Replaced & Tested Satisfactorily1998-01-16016 January 1998
- on 971218,EDGs Were Simultaneously Inoperable While Unit 1 Was at Power Due to Time Delay Relay 2 Failing to Meet Acceptance Criteria.Unit 1/2 EDG TD2 Relay Was Replaced & Tested Satisfactorily
05000254/LER-1997-029-01, :on 970316,Units 1 & 2 RBM Channel Functional Testing Were Not Accomplished within 7 Days Prior to Startup Required by TS Due to Misinterpretation of Ts.Investigation (PIF 97-3147, Nts 25420097SCAQ00088) Was Performed1998-01-0909 January 1998
- on 970316,Units 1 & 2 RBM Channel Functional Testing Were Not Accomplished within 7 Days Prior to Startup Required by TS Due to Misinterpretation of Ts.Investigation (PIF 97-3147, Nts 25420097SCAQ00088) Was Performed
05000254/LER-1997-024-02, :on 971201,required 10CFR50.59 Summary Evaluation for Change to UFSAR Not Submitted to NRC Due to an Administrative Oversight Error.Revised Procedure Qcap 0500-01, Processing 10CFR50.59 Ses1997-12-22022 December 1997
- on 971201,required 10CFR50.59 Summary Evaluation for Change to UFSAR Not Submitted to NRC Due to an Administrative Oversight Error.Revised Procedure Qcap 0500-01, Processing 10CFR50.59 Ses
05000265/LER-1997-012-06, :on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted1997-12-18018 December 1997
- on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted
05000254/LER-1997-021-01, :on 970826,discrepancies Found Between Safe Shutdown (Ssd) Procedures & Fire Protecton Rept Which Led T) Declaration That Nine Ssd Paths Inoperable.Caused by Lack of Process.Performed PRA for Fire1997-12-16016 December 1997
- on 970826,discrepancies Found Between Safe Shutdown (Ssd) Procedures & Fire Protecton Rept Which Led T) Declaration That Nine Ssd Paths Inoperable.Caused by Lack of Process.Performed PRA for Fire
05000265/LER-1997-015-05, :on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time1997-12-0808 December 1997
- on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time
05000254/LER-1997-025-01, :on 961216,failed to Calibr APRM to Flow Signal within Required Interval.Caused by Inadequate Change Mgt.Counselled Personnel Responsible for Change,Conducted Trend Investigation & Revised Procedures1997-12-0505 December 1997
- on 961216,failed to Calibr APRM to Flow Signal within Required Interval.Caused by Inadequate Change Mgt.Counselled Personnel Responsible for Change,Conducted Trend Investigation & Revised Procedures
05000254/LER-1997-023-01, :on 970317,required TS Surveillance Was Not Performed Prior to Reactor Mode Change on 4 Occasions.Caused by Inadequate Procedures Associated W/Implementation of Ts. Will Incorporate Predefined Surveillance Work Requests1997-11-25025 November 1997
- on 970317,required TS Surveillance Was Not Performed Prior to Reactor Mode Change on 4 Occasions.Caused by Inadequate Procedures Associated W/Implementation of Ts. Will Incorporate Predefined Surveillance Work Requests
05000254/LER-1997-022-01, :on 971015,CR HVAC Sys Declared Inoperable Due to Inadequate Cooling Water Flow.Caused by Lifting of SWS Relief Valve.Revised & Reviewed Test Procedure1997-11-12012 November 1997
- on 971015,CR HVAC Sys Declared Inoperable Due to Inadequate Cooling Water Flow.Caused by Lifting of SWS Relief Valve.Revised & Reviewed Test Procedure
05000265/LER-1997-003-02, :on 970321,significant Fouling Was Discovered in 2B Core Spray Room Cooler During pre-cleaning Insp. Caused by Debris Stirred Up by Hydrolyzing Performed During Q2R13 on EDG Cws.Coolers Planned to Be Installed on Unit 11997-10-24024 October 1997
- on 970321,significant Fouling Was Discovered in 2B Core Spray Room Cooler During pre-cleaning Insp. Caused by Debris Stirred Up by Hydrolyzing Performed During Q2R13 on EDG Cws.Coolers Planned to Be Installed on Unit 1
05000265/LER-1997-005-02, :on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts1997-10-23023 October 1997
- on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts
05000265/LER-1997-011-05, :on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals1997-10-0202 October 1997
- on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals
05000265/LER-1997-006-01, :on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C11997-09-26026 September 1997
- on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C1
05000265/LER-1997-010-05, :on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled1997-09-12012 September 1997
- on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled
05000254/LER-1997-016-01, :on 970509,DG Cw IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 11997-09-0303 September 1997
- on 970509,DG Cw IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 1
05000254/LER-1997-019-01, :on 970808,TS 3.0.C Was Entered Because No LCO Was Available for Secondary Containment When Both Doors for Interlock Were Opened Simultaneously.Verified Proper Operation1997-09-0303 September 1997
- on 970808,TS 3.0.C Was Entered Because No LCO Was Available for Secondary Containment When Both Doors for Interlock Were Opened Simultaneously.Verified Proper Operation
05000265/LER-1997-006-06, :on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed1997-08-27027 August 1997
- on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed
05000254/LER-1997-018-01, :on 970721,determined That RHRSW Valves Associated W/Rhr Pumps Were Not Included in Monthly Valve Surveillance.Caused by Inadequate Procedure Development. Verified Valves to Be in Corrected Position1997-08-20020 August 1997
- on 970721,determined That RHRSW Valves Associated W/Rhr Pumps Were Not Included in Monthly Valve Surveillance.Caused by Inadequate Procedure Development. Verified Valves to Be in Corrected Position
05000254/LER-1997-017-01, :on 970623,Unit 1 Entered 12 Hour Hot Shutdown LCO Inappropriately.Caused by Scheduling Error by Lup.Lups Were Counseled to Avoid Necessary Entry Into 12 H Hot Shutdown LCO1997-08-12012 August 1997
- on 970623,Unit 1 Entered 12 Hour Hot Shutdown LCO Inappropriately.Caused by Scheduling Error by Lup.Lups Were Counseled to Avoid Necessary Entry Into 12 H Hot Shutdown LCO
05000265/LER-1997-009-05, :on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas1997-08-0707 August 1997
- on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas
05000265/LER-1997-008-05, :on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable1997-07-28028 July 1997
- on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable
05000265/LER-1992-005-02, :on 920125,initiation of a Train Standby Gas Treatment Sys Occurred.Caused by Failure of Bypass Switch Mounting Bracket Due to Vibrations.Remounted Bypass Switch Back in 902-10 Panel & Tightened & Checked Other Switches1997-07-0808 July 1997
- on 920125,initiation of a Train Standby Gas Treatment Sys Occurred.Caused by Failure of Bypass Switch Mounting Bracket Due to Vibrations.Remounted Bypass Switch Back in 902-10 Panel & Tightened & Checked Other Switches
05000254/LER-1997-020-01, :on 970519,B-train Control Room Ventilation Sys Became Inoperable When AHU Breaker Tripped When Performing Monthly Surveillance.Cause Could Not Be Determined.Circuitry Testing Completed1997-06-18018 June 1997
- on 970519,B-train Control Room Ventilation Sys Became Inoperable When AHU Breaker Tripped When Performing Monthly Surveillance.Cause Could Not Be Determined.Circuitry Testing Completed
05000265/LER-1997-004-06, :on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed1997-05-29029 May 1997
- on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed
1999-06-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000254/LER-1999-004-03, :on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-021999-10-12012 October 1999
- on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-02
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure1999-10-0707 October 1999
- on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20216H8481999-09-23023 September 1999 Safety Evaluation Supporting Amends 190 & 187 to Licenses DPR-29 & DPR-30,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 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210U7831999-08-0404 August 1999 Safety Evaluation Supporting Amends 189 & 186 to Licenses DPR-29 & DPR-30,respectively ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196F4261999-06-25025 June 1999 Safety Evaluation Supporting Amends 188 & 185 to Licenses DPR-29 & DPR-30,respectively 05000265/LER-1999-002-04, :on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 9907151999-06-25025 June 1999
- on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 990715
05000254/LER-1999-004-02, :on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised1999-06-18018 June 1999
- on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised
ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20207E1621999-05-25025 May 1999 Rev 1 to Quad Cities IPEEE, Consisting of Revised Chapter 4.0 Re Internal Fire Analysis ML20210H3501999-05-25025 May 1999 Rev 1 to Quad Cities Station IPEEE Submittal Rept 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 05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance1999-05-12012 May 1999
- on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205F4791999-03-31031 March 1999 Safety Evaluation Supporting Amends 187 & 184 to Licenses DPR-29 & DPR-30,respectively SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205D4171999-03-26026 March 1999 Safety Evaluation Supporting Amends 186 & 183 to Licenses DPR-29 & DPR-30,respectively ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20204D9751999-03-17017 March 1999 Safety Evaluation Supporting Amends 185 & 182 to Licenses DPR-29 & DPR-30,respectively ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20198S6841998-12-22022 December 1998 Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves 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 SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With 05000254/LER-1998-001-01, :on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation1998-10-27027 October 1998
- on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation
05000265/LER-1998-006-04, :on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-061998-10-15015 October 1998
- on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-06
SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With 1999-09-30
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