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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With1999-10-22022 October 1999
- on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With
05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With1999-09-20020 September 1999
- on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With
05000317/LER-1999-004, :on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With1999-08-23023 August 1999
- on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With
05000317/LER-1999-005, :on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With1999-08-23023 August 1999
- on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With
05000317/LER-1999-003, :on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With1999-07-30030 July 1999
- on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With
05000317/LER-1999-002, :on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With1999-05-25025 May 1999
- on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With
05000317/LER-1997-010, :on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With1999-01-29029 January 1999
- on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With
05000317/LER-1998-009, :on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With1999-01-0808 January 1999
- on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With
05000317/LER-1998-008, :on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With1998-11-11011 November 1998
- on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With
05000318/LER-1998-004-01, :on 980723,manual Plant Trip Occurred Due to Moisture Separator Reheater Vent Line Rupture.Caused by Flow Accelerated Corrosion.Replaced Ruptured Pipe & Completed Insp of Other Small Bore high-energy Piping1998-08-24024 August 1998
- on 980723,manual Plant Trip Occurred Due to Moisture Separator Reheater Vent Line Rupture.Caused by Flow Accelerated Corrosion.Replaced Ruptured Pipe & Completed Insp of Other Small Bore high-energy Piping
05000318/LER-1998-005-01, :on 980725,initiated Plant Cooldown Due to RCS Pressure Boundary Leakage.Caused by Crack in Inconel Alloy 600-type Weld Filler Matl of Nozzle.Leaking Penetration Was Repaired from Outside of Pressurizer1998-08-24024 August 1998
- on 980725,initiated Plant Cooldown Due to RCS Pressure Boundary Leakage.Caused by Crack in Inconel Alloy 600-type Weld Filler Matl of Nozzle.Leaking Penetration Was Repaired from Outside of Pressurizer
05000318/LER-1998-003-01, :on 980507,relays out-of-calibration Were Noted Due to Bumped Dial & Actions Not Taken.Caused by Improperly Installed Cover.Technicians Will Be Trained on Event & Protective Covers Will Be Clearly Marked1998-06-0404 June 1998
- on 980507,relays out-of-calibration Were Noted Due to Bumped Dial & Actions Not Taken.Caused by Improperly Installed Cover.Technicians Will Be Trained on Event & Protective Covers Will Be Clearly Marked
05000317/LER-1998-007, :on 980404,eight of Sixteen MSSVs on Unit 1 Lifted at Pressure Above Setpoint Required in Tech Specs During as-found Lift Test.Cause of Event Currently Under Investigation.Reset Failed Valves1998-05-0404 May 1998
- on 980404,eight of Sixteen MSSVs on Unit 1 Lifted at Pressure Above Setpoint Required in Tech Specs During as-found Lift Test.Cause of Event Currently Under Investigation.Reset Failed Valves
05000317/LER-1998-006, :on 980325,1B DG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Nylon in Governors Shutdown Solenoid Valve.Conducted Review1998-04-21021 April 1998
- on 980325,1B DG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Nylon in Governors Shutdown Solenoid Valve.Conducted Review
05000317/LER-1998-005, :on 980312,spare Reactor Trip Breaker Did Not Meet TS Requirements.Caused by Inadequate Procedures.Revised Procedures to Include Testing Requirements for Spare Breaker1998-04-13013 April 1998
- on 980312,spare Reactor Trip Breaker Did Not Meet TS Requirements.Caused by Inadequate Procedures.Revised Procedures to Include Testing Requirements for Spare Breaker
05000318/LER-1998-002-01, :on 980305,failure of Handswitch Passive Contact to Close Occurred.Caused by Contacts in Lower Contact Block of Handswitch Did Not Close as Designed. Handswitch Replaced1998-04-0707 April 1998
- on 980305,failure of Handswitch Passive Contact to Close Occurred.Caused by Contacts in Lower Contact Block of Handswitch Did Not Close as Designed. Handswitch Replaced
05000317/LER-1998-004, :on 980303,battery Charger Circuit Breakers Were Noted Missing from Seismic Positioner.Caused by Quality Issue Related to Vendor.All safety-related 480-volt Circuit Breakers Have Been Inspected1998-04-0101 April 1998
- on 980303,battery Charger Circuit Breakers Were Noted Missing from Seismic Positioner.Caused by Quality Issue Related to Vendor.All safety-related 480-volt Circuit Breakers Have Been Inspected
05000318/LER-1998-001-01, :on 980113,unit 2B EDG Had Been Inoperable for 15 Days.Caused by Speed Switch Adapter Failure.Inspected/ Replaced Other Diesel Speed Switch Adapters to Ensure Spring Clips Are Not Degraded1998-02-12012 February 1998
- on 980113,unit 2B EDG Had Been Inoperable for 15 Days.Caused by Speed Switch Adapter Failure.Inspected/ Replaced Other Diesel Speed Switch Adapters to Ensure Spring Clips Are Not Degraded
05000317/LER-1998-002, :on 980107,fire Hose Station & Room Sprinkler Sys Were Noted out-of-service.Caused by Operating Mislabeled Valve.Correct Tagout Boundary Was Established & Verified by Addl Complete Walkdown of Tagout1998-02-0909 February 1998
- on 980107,fire Hose Station & Room Sprinkler Sys Were Noted out-of-service.Caused by Operating Mislabeled Valve.Correct Tagout Boundary Was Established & Verified by Addl Complete Walkdown of Tagout
05000317/LER-1998-003, :on 980113,damage Was Found on Stanchion & Restraining Steel of Unit 1 LPSI Sys Pipe Support Location on Common Discharge Line.Caused by LPSI Pump Discharge Check Valve Slam(S).Pipe Support Was Removed1998-02-0606 February 1998
- on 980113,damage Was Found on Stanchion & Restraining Steel of Unit 1 LPSI Sys Pipe Support Location on Common Discharge Line.Caused by LPSI Pump Discharge Check Valve Slam(S).Pipe Support Was Removed
05000317/LER-1998-001, :on 980104,Unit 1 Entered Condition Outside of Tech Specs Due to Having Both Secondary Control Element Assembly Position Indications out-of-svc.Caused by Position Indication Being Inoperable.Procedure Revised1998-02-0303 February 1998
- on 980104,Unit 1 Entered Condition Outside of Tech Specs Due to Having Both Secondary Control Element Assembly Position Indications out-of-svc.Caused by Position Indication Being Inoperable.Procedure Revised
05000317/LER-1997-007, :on 971029,discovered That Three Surveillance Test Procedures Were Not Completed within Test Interval. Caused by Excessive Use of 25% Grace Period Allowed for Completion of Surveillance.Revised Procedures1997-12-0101 December 1997
- on 971029,discovered That Three Surveillance Test Procedures Were Not Completed within Test Interval. Caused by Excessive Use of 25% Grace Period Allowed for Completion of Surveillance.Revised Procedures
05000317/LER-1997-009, :on 971024,automatic Reactor Trip Occurred. Caused by Failure to Properly Terminate Electrical Lead on Condenser Vacuum Breaker Handswitch During Prior Handswitch Maintenance.Over 200 Similar Connection Insp1997-11-20020 November 1997
- on 971024,automatic Reactor Trip Occurred. Caused by Failure to Properly Terminate Electrical Lead on Condenser Vacuum Breaker Handswitch During Prior Handswitch Maintenance.Over 200 Similar Connection Insp
05000317/LER-1997-008, :on 971017,two Reactor Protective Sys Channels Were OOS During Test.Caused by Significant Variations in Power Supply Voltages.Requested Maint to Back Out of Calibr of Channel C & Return Channel to Svc1997-11-12012 November 1997
- on 971017,two Reactor Protective Sys Channels Were OOS During Test.Caused by Significant Variations in Power Supply Voltages.Requested Maint to Back Out of Calibr of Channel C & Return Channel to Svc
05000317/LER-1996-001, :on 960117,SRW Heat Exchanger Microfouling High than Assumed in Design Basis Occurred.Caused by Original Design Calculations for SRW Heat Exchangers Assumed Min SRW Flow.New Operability Limits Implemented1997-10-21021 October 1997
- on 960117,SRW Heat Exchanger Microfouling High than Assumed in Design Basis Occurred.Caused by Original Design Calculations for SRW Heat Exchangers Assumed Min SRW Flow.New Operability Limits Implemented
05000317/LER-1997-006, :on 970722,cable Spreading Room Halon Sys Was Inoperable.Caused by Personnel Error.Operations Personnel Reminded of Possibility of Inoperable Dampers Affecting Halon Sys Operability1997-08-21021 August 1997
- on 970722,cable Spreading Room Halon Sys Was Inoperable.Caused by Personnel Error.Operations Personnel Reminded of Possibility of Inoperable Dampers Affecting Halon Sys Operability
05000317/LER-1997-004, :on 970602,trip Bypasses Were Not Removed When Thermal Power Was Increased Above 15%.Caused by Failure to Recognize Difference Between Nuclear Instrument & Delta-T. Revised Plant Procedures1997-07-0202 July 1997
- on 970602,trip Bypasses Were Not Removed When Thermal Power Was Increased Above 15%.Caused by Failure to Recognize Difference Between Nuclear Instrument & Delta-T. Revised Plant Procedures
05000317/LER-1997-005, :on 970529,reactor Coolant Sys Leak Occurred. Caused by Failed Compression Fitting.Conducted Review of Compression Fitting Maint Performed on High Pressure Systems & Completed Insps of Compression Fittings1997-06-30030 June 1997
- on 970529,reactor Coolant Sys Leak Occurred. Caused by Failed Compression Fitting.Conducted Review of Compression Fitting Maint Performed on High Pressure Systems & Completed Insps of Compression Fittings
05000317/LER-1997-003-01, :on 970424,fuel Moved in Spent Fuel Pool Without Charcoal Absorber Banks Being in Svc.Caused by Personnel Error.Fuel Movement Suspended Until All Appropriate Personnel Could Be Trained1997-05-23023 May 1997
- on 970424,fuel Moved in Spent Fuel Pool Without Charcoal Absorber Banks Being in Svc.Caused by Personnel Error.Fuel Movement Suspended Until All Appropriate Personnel Could Be Trained
05000318/LER-1997-003, :on 970423,chemistry Sampling Was Not Performed as Required by TS 3.4.7 Due to Insufficient Consideration of Precise Wording of TS on Part of Chemistry Personnel.Ts Will Be Clarified When Improved TS Are Implemented1997-05-21021 May 1997
- on 970423,chemistry Sampling Was Not Performed as Required by TS 3.4.7 Due to Insufficient Consideration of Precise Wording of TS on Part of Chemistry Personnel.Ts Will Be Clarified When Improved TS Are Implemented
05000318/LER-1997-002-01, :on 970405,containment Purge Valve Isolation Sys TS Violation Occurred.Caused by Inaccurate Implementation of TS 3.9.9.Personnel Air Lock Interlocks Restored1997-05-0505 May 1997
- on 970405,containment Purge Valve Isolation Sys TS Violation Occurred.Caused by Inaccurate Implementation of TS 3.9.9.Personnel Air Lock Interlocks Restored
05000318/LER-1997-001-01, :on 970401,refueling Machine Overload Protective Circuitry Was Inoperable Due to Failure to Correctly Translate Refueling Machine Circuitry Design Into Ts.Mod to Overload Bypass Was Installed1997-04-30030 April 1997
- on 970401,refueling Machine Overload Protective Circuitry Was Inoperable Due to Failure to Correctly Translate Refueling Machine Circuitry Design Into Ts.Mod to Overload Bypass Was Installed
05000317/LER-1997-002, :on 970220,misread TS Requirements Resulted in Inadequate Test.Caused by Lack of Strict Adherence to Wording of Plants TS Requirements.Edgs 1B,2A & 2B Were Successfully Tested & Returned to Svc1997-03-24024 March 1997
- on 970220,misread TS Requirements Resulted in Inadequate Test.Caused by Lack of Strict Adherence to Wording of Plants TS Requirements.Edgs 1B,2A & 2B Were Successfully Tested & Returned to Svc
05000317/LER-1997-001, :on 970110,spent Fuel Moved W/Ventilation Sys Inoperable & Missed Surveillance Occurred.Cause Analysis Being Performed to Determined Casual Factors & Generic Implications for Event.Surveillance Performed1997-02-10010 February 1997
- on 970110,spent Fuel Moved W/Ventilation Sys Inoperable & Missed Surveillance Occurred.Cause Analysis Being Performed to Determined Casual Factors & Generic Implications for Event.Surveillance Performed
05000318/LER-1996-006, :on 961210,discovered EDG Had Been Inoperable for Six Days.Caused by Personnel Error.Checked Fuse Holder Covers,Conducted Tailgate Training & Revised Procedure Re Installation of Fuse Holder Covers1997-01-10010 January 1997
- on 961210,discovered EDG Had Been Inoperable for Six Days.Caused by Personnel Error.Checked Fuse Holder Covers,Conducted Tailgate Training & Revised Procedure Re Installation of Fuse Holder Covers
05000318/LER-1996-002, :on 960522,missed Fire Watch Occurred Due to Personnel Error.Root Cause Analysis Has Been Completed. Plant Mgt Reemphasized to Site Personnel Importance of & Requirements for Fire Watches1996-12-31031 December 1996
- on 960522,missed Fire Watch Occurred Due to Personnel Error.Root Cause Analysis Has Been Completed. Plant Mgt Reemphasized to Site Personnel Importance of & Requirements for Fire Watches
05000318/LER-1996-005, :on 961117,automatic Reactor Trip Occurred Due to Closure of Feedwater Regulating Valve.Magnetic Particle Examination Was Conducted on New,Replacement Spring Retainers.No Indications Were Found1996-12-17017 December 1996
- on 961117,automatic Reactor Trip Occurred Due to Closure of Feedwater Regulating Valve.Magnetic Particle Examination Was Conducted on New,Replacement Spring Retainers.No Indications Were Found
05000318/LER-1996-004-01, :on 960926,missed Surveillance Occurred Due to Less than Adequate Technical Review of Stp.Procedures Revised1996-10-28028 October 1996
- on 960926,missed Surveillance Occurred Due to Less than Adequate Technical Review of Stp.Procedures Revised
05000317/LER-1995-005, :on 951109,manual Reactor Trip Occurred.Caused by Failure of Digital Feedwater Control Module FIC-1111. Reviewed Design Engineering Standards & Existing FP 2000 Digital Controllers Are Being Replaced1996-10-10010 October 1996
- on 951109,manual Reactor Trip Occurred.Caused by Failure of Digital Feedwater Control Module FIC-1111. Reviewed Design Engineering Standards & Existing FP 2000 Digital Controllers Are Being Replaced
05000317/LER-1996-004, :on 960802,two Asi Channels OOS Due to Reversed Nuclear Instrumentation Leads.Leads Were Correctly Reconnected When Plant Was Brought Down on 9608021996-09-0303 September 1996
- on 960802,two Asi Channels OOS Due to Reversed Nuclear Instrumentation Leads.Leads Were Correctly Reconnected When Plant Was Brought Down on 960802
05000318/LER-1996-003-01, :on 960619,discovered Missed Fire Protection Compensatory Action.Caused by Personnel Error.Provided Awareness Training to Personnel Re Fire Protection Compensatory Actions Expectations1996-07-17017 July 1996
- on 960619,discovered Missed Fire Protection Compensatory Action.Caused by Personnel Error.Provided Awareness Training to Personnel Re Fire Protection Compensatory Actions Expectations
05000318/LER-1996-002-01, :on 960522,fire Watch Missed.Caused by Personnel Error.Counseled Personnel Re Event1996-06-21021 June 1996
- on 960522,fire Watch Missed.Caused by Personnel Error.Counseled Personnel Re Event
05000317/LER-1996-003, :on 960423,discovered Holes in Containment Sump Screen Larger than Described in Ufsar.Holes Most Likely Installed During Plant Const.Sump Screens Visually Inspected & Repaired1996-05-24024 May 1996
- on 960423,discovered Holes in Containment Sump Screen Larger than Described in Ufsar.Holes Most Likely Installed During Plant Const.Sump Screens Visually Inspected & Repaired
05000317/LER-1996-002, :on 960410,required Fire Watch Missed.Caused by Lack of Fire Watch Ownership.Circumstances of Event Will Be Reviewed W/Appropriate Groups1996-05-14014 May 1996
- on 960410,required Fire Watch Missed.Caused by Lack of Fire Watch Ownership.Circumstances of Event Will Be Reviewed W/Appropriate Groups
05000318/LER-1996-001-01, :on 960227,breakers 552-41,552-21 & 552-61 Tripped Open in Plant Switchyard.Caused by Failure of Auxiliary Relay Card in Breaker 552-41.Failed Relay Card Replaced1996-03-28028 March 1996
- on 960227,breakers 552-41,552-21 & 552-61 Tripped Open in Plant Switchyard.Caused by Failure of Auxiliary Relay Card in Breaker 552-41.Failed Relay Card Replaced
05000317/LER-1996-001, :on 960117,determined That SW HX Microfouling Higher than Assumed in Design Basis.Caused by Design Deficiency.Conservative Operability Limits Established & Bay Temp & SW HXs Being Monitored1996-02-16016 February 1996
- on 960117,determined That SW HX Microfouling Higher than Assumed in Design Basis.Caused by Design Deficiency.Conservative Operability Limits Established & Bay Temp & SW HXs Being Monitored
05000317/LER-1995-006, :on 951116,manual Reactor Trip Occurred Due to Loss of 12 SG Feed Pump.Caused Oil Losses Allowing Pressure to Drop Before Standby Pump Could Restore Pressure.Trip Mechanism & Thrust Cleaned & Adjusted1995-12-13013 December 1995
- on 951116,manual Reactor Trip Occurred Due to Loss of 12 SG Feed Pump.Caused Oil Losses Allowing Pressure to Drop Before Standby Pump Could Restore Pressure.Trip Mechanism & Thrust Cleaned & Adjusted
05000317/LER-1995-005-01, :on 951109,manual Reactor Trip Occurred Due to Increasing SG 11 Water Level.Caused by Failure of Digital Control Module FIC-1111.Controller Sent to Vendor for Troubleshooting & Root Cause Analysis1995-12-11011 December 1995
- on 951109,manual Reactor Trip Occurred Due to Increasing SG 11 Water Level.Caused by Failure of Digital Control Module FIC-1111.Controller Sent to Vendor for Troubleshooting & Root Cause Analysis
05000317/LER-1995-004-01, :on 950816,inoperable Fire Barrier Penetration Seal Was Discovered.Caused by Inadequate Engineering Oversight & Less than Adequate Surveillance Procedure.Sealed Penetration Seal1995-09-15015 September 1995
- on 950816,inoperable Fire Barrier Penetration Seal Was Discovered.Caused by Inadequate Engineering Oversight & Less than Adequate Surveillance Procedure.Sealed Penetration Seal
05000317/LER-1995-003-01, :on 950730 & 31,entered TS 3.0.3 Due to High Bay Water Temps.Administration Limit for Bay Water Temp Raised & Current Unit 1 & Unit 2 SW Tube Type HXs Will Be Replaced1995-08-28028 August 1995
- on 950730 & 31,entered TS 3.0.3 Due to High Bay Water Temps.Administration Limit for Bay Water Temp Raised & Current Unit 1 & Unit 2 SW Tube Type HXs Will Be Replaced
1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With1999-10-22022 October 1999
- on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With
ML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With 05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With1999-09-20020 September 1999
- on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With
ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20211J3531999-09-0101 September 1999 Safety Evaluation Supporting Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-005, :on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With1999-08-23023 August 1999
- on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With
05000317/LER-1999-004, :on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With1999-08-23023 August 1999
- on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With
ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-003, :on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With1999-07-30030 July 1999
- on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With
ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-002, :on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With1999-05-25025 May 1999
- on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With
ML20206U7031999-05-18018 May 1999 Rev 1 to Ran 97-031, Main CR Fire Analysis for IPEEE Section 4-1 ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20205J8331999-04-0707 April 1999 Safety Evaluation Concluding That Security Lighting,Portable Lighting & Helmet Lights,As Described by Licensee Satisfies Underlying Purpose of 10CFR50,App R,Section Iii.J.Grants Licensee Request for Exemption ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20204B5961999-03-17017 March 1999 Corrected Page 7 to SER for Amend 205 for License DPR-69. Staff Deleted Word Not on Line One of Page 7 ML20207L2991999-03-0808 March 1999 Safety Evaluation Supporting Amend 205 to License DPR-69 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons 05000317/LER-1997-010, :on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With1999-01-29029 January 1999
- on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With
ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 05000317/LER-1998-009, :on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With1999-01-0808 January 1999
- on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With
ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20196J6771998-12-0808 December 1998 Safety Evaluation Supporting Amends 229 & 204 to FOLs DPR-53 & DPR-69,respectively ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative 05000317/LER-1998-008, :on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With1998-11-11011 November 1998
- on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With
ML20195D4271998-11-0505 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-69 ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With 1999-09-30
[Table view] |
text
4 0
B ALTIMORE GAS AND ELECTRIC CALVERT CLIFFS NUCLEAR POWER PLANT 1650 CALVERT CLIFFS PARKWAY
- LUSBY. MARYLAND 20657-4702 CHARLES H, CAUSE PLANT G&NERAL MANAGEA cALVERT CL,pr3 June 29, 1993 U S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
Document Control Desk SUBJ ECT :
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2; Docket Nos. 50-317 and 50-318; License Nos. DPR 53 and DPR 69 Licensee Event Report 93-002, Revision 01 Missed Surveillance Requirements Due to Software Manual Error 3
Centlemen:
The attached report is being sent to you as required under 10 CFR 50.73 guidelines.
Should you have any questions regarding this report, we will be pleased to discuss them with you.
Very truly yours, f,
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D. A. Brune, Esquire J. E. Silberg, Esquire R. A.
Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R.
I. McLean, DNR J. H. Walter, PSC Director, Office of Management Information and Program Control 020074 i
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NRC FORM 366 U. S. NUCLEAR REGULATOHY COMMISSION W
EUTIMATED BURCIN PER Ef#CNSE TO 03MFLYWITH THIS INFORMATION CCt1ECRON REQUEST: Sa0 KR TCWNO COMMENTS REGMONG LICENSEE EVENT REPORT (LER)
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F ACILITY NAME (1)
DOCKET NUMBER (2)
P AGE (3)
Calvert Clif f s, Unit 1 05000 317 1 OF 04 i
TITLE (4)
Missed Surveillance Requirements Due to Sof tware Manual Error EVENT DATE (5)
LER NUMBER (6) l REPORT DATE (7)
OTHER FACILITIES INVOLVED 18)
- b II ECMM ESION MONTH DAY YEAR MONTH DAY YEAR YEAR Calvert Cuffs, U2 l 05000 318 NWBER NUMBER 02 05 93 93
- - 002 01 06 29 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REOUtPEMENTS OF 90 CFR -fChece one or emre) (11) 1 MODE (9) j 20.402(b) 20,405(c) l 50.73(a)(2)(iv) 73.7, gg j 20.405(aH1)(i)
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LICENSEE OONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Code)
W. D. Maki Compliance Engineer 410 260-3651 COMPLETE ONE LINE FoR EACH COMPONENT FAILURE DESCRIBED IN TIUS REPORT (13) l ENW M CAUSE SYSTEM COMPONENT
CAUSE
SYSTEM l COMPONENT TURER NPRDS TURER NPRDS I
X lD C490 NO l
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH I DAY hYEARi SUBMISSION l
YES X
NO of van comrdern FrPFCTFD SUBMISSION DATD DATE (15)
I ABS i RACT (Lmt to 1400 spaces. t e., approximately15 sen<pe-space ypewrmen ones) (16)
Calvert Cliffs uses the Better Axial Shape Selector System (BASSS) version 3.3 computer code.
This system monitors incore Axial Shape Index (ASI) and provides various alarm functions.
The software vendor discovered an error in its user's manual which the vendor uses in updating BASSS's data-input library. The error rendered oru alarm function inoperable, resulting in Units 1 and 2 not fulfilling Technical Specification Surveillance Requirement 4.2.5.1.
This Surveillance requires verification of incore ASl within limits every twelve hours. The cause of the user manual error was failure of the vendor's quality assurance procedures to require independent review of user's manuals.
Corrective actions included manual performance of the S urve illanc'e, correcting BASSS's data-input library, verifying BASSS a
operable, and reviewing applicable sections of the user manual.
After l
issuance of the software but prior to the discovery of this event, the vendor i
upgraded its quality assurance procedures to require independent review of software documentation.
Baltimore Cas and Electric Company has audited the Vendor's quality assurance program and found it to be satisfactory.
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DESCRIPTION OF E\\ :T on April 12, 1991 and July 21, 1992, Calvert Cliffs Nuclear Power Plant installed the Better Axial Shape Selector System (3ASSS) version 3.3 on the Units 2 and 1 plant computers respectively.
The BASSS computer code calcula es incore axial shape index (AS1) in real time.
Measuring incore ASI and maintaining it within prescribed Technical Specification (TS) limi s ensures that plant parameters do not exceed thermal / hydraulic limitations.
Because of an unrelated self-assessment requested by Baltimore Gas a d Electric Company (BC&E), the software vendor was reviewing the BASSS 3.3 user nanual on February 4, 1993.
's a result of this review, a user-man al error was discovered.
After evaluating the error, the vendor notified BC&E on February 5, 1993.
The user-manual error resulted in '.ncorrect sequencing of program input data, rendering an important alarm function inoperable.
The program input data is provided to BC&E on a refuel _ng outage basis. The affected alarm wa;ns lionsed plant operators when ASI exceeds the Small-8:eak Loss-of-Coolant Accident (LOCA)
ASI limit.
Operating within the limit ensures plant conditions remain within the analyzed boundaries for this accident. Without the alar-the plant was relying on a slightly less conservative BASSS alarm to infor them of an unsatisfactory ASI condition. A review of historical plant data showed that the more conservative ASI limits were never violated.
This particular alarm function is necessary to meet the TS 4.5.2.1 surveillance.
TS 4.5.2.1 requires verification every twelve hours that ASI does not exceed its limits. As a result of the user-manual problem, these ASI verifications were not complete. Units 2 and I were started-up on April 28, 1991 and August 16, 1992 respectively.
They operated for 566 and 169 days in this condition.
Calvert Cliffs immediately took alternate, compensatory measures to perform the TS 4.2.5.1 surveillances.
The vendor issued a Part 21 report concerning the error on February 12, 1993.
II.
CAUSE OF EVE'iT The software was procured under the vendor's 10 CFR 50 Appendix 3 quality assurance Program.
Following discovery of the event, the vendor conducted a root cause analysis and determined that the root cause was failure of the l
quality assurance procedures in E-e at the time to require independent review of
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i user nianuals.
The manual containing the error was developed in 1989, prior to a i
1990 upgrade of the vendor's procedures whica instituted such a recsirement.
l a
J Few cnline software products are provided by this vendor. The other ones ths.
2 are do not require input-data updating.
III.
ANALYSIS OF EVENT
This event was not safety significant. Actual plant ASI values remained within i
the small-break LOCA ASI limit during the operating periods. Additionally, Nuclear Fuel. Management receives daily ASI trend c'ata which is reviewed i
periodically.
If ASI had violated any limits, earlier discovery of the manual I
error would have been likely.
The failure to perform a TS Surveillance Requirement is reportable under 10 CFR 50.73(a)(2)(1)(A) as a condition prohibited by plant Technical i
SpecificaH ons.
i IV.
CORkiCTIVE ACTIONS I
Immediate Corrective Actions
f f
A.
The vendor and SC6E checked the remaining input data against the l
BASSS code.
No other errors were found.
l i
B.
Immediate action was taken to perform the surveillances manually 4
until the vandor's corrected input data was installed on l
February 12, 1993, i
C.
Although the problem was unique to Calvert Cliffs, the vendor notified all other code users of the error.
i i
D.
The BASSS coding and related user-manual sections were reviewed. No similar problems were discovered I
Actions to Prevent Recurrence:
E.
The vendor corrected de error in the user man 1sl.
l F.
The vendor's quality assurance procedures were updated in August 1990 to require incependent verification of software and related I
documentation.
The procedures were further revised in April 1993, f
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.U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150 0104 ts4a EXPIRES 5/31/95
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TEXT CONTINUATION REGULATORf COMus3CN, WASHINGTON. DC 205554M. ANO TO THE PAPEPWORK REDUCTON PRCUECT Q1SO41046 OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20501 5
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F ActuYY NAME (1)
DOCKET NUMBER (a LER NUMBER {3)
PAGE (4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 002 01 04 0F 04
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% o.ooem. c.on ne NRC ro, 3.sA> (i7) strengthening software documenti. tion verification and validation requirements. These upgrades are sufficient to prevent similar l
events.
G.
W'iEs Vendor Audits Unit completed a review of the vendor's quality program and found this area to be satisfactory.
V.
ADDITIONAL INFORMATION
t i
A.
Component and System Identification described in this report:
IEEE 803A/83 IEEE 805/84 Component or System Funct. Ident. System Code (s)
Plant Jomputer CPU ID 4
3.
There have been no similar reportable events at Calvert Cliffs.
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05000318/LER-1993-001-01, :on 930220,plant Found to Be in Condition Outside Design Basis When Pressurizer Code Safety Valve Found W/Lift Setpoints Due to Imprecision Associated W/Test Methodology.Valves Setpoints Will Be Verified |
- on 930220,plant Found to Be in Condition Outside Design Basis When Pressurizer Code Safety Valve Found W/Lift Setpoints Due to Imprecision Associated W/Test Methodology.Valves Setpoints Will Be Verified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000317/LER-1993-001, :on 930202,both CR Air Conditioning Trains Declared Inoperable & Plant Entered TS 3.0.3.Caused by Insufficient Sys Refrigerant Inventory.Procedures for Maint Will Be Revised Re Weight of Refrigerant |
- on 930202,both CR Air Conditioning Trains Declared Inoperable & Plant Entered TS 3.0.3.Caused by Insufficient Sys Refrigerant Inventory.Procedures for Maint Will Be Revised Re Weight of Refrigerant
| 10 CFR 50.73(a)(2)(1) | 05000318/LER-1993-002-01, :on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve Opened |
- on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve Opened
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | 05000317/LER-1993-002, :on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances Performed |
- on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(1) | 05000318/LER-1993-003-01, :on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed |
- on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000317/LER-1993-003, :on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be Reinforced |
- on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be Reinforced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000318/LER-1993-004-01, :on 931202,axial Shape Index Channel Error Occurred Due to Insufficent Trouble Shooting Review.Caused by Insufficent Maint Testing Performed Prior to Declaring Channel Operable.Procedures Revised |
- on 931202,axial Shape Index Channel Error Occurred Due to Insufficent Trouble Shooting Review.Caused by Insufficent Maint Testing Performed Prior to Declaring Channel Operable.Procedures Revised
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000317/LER-1993-004, :on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant Startup |
- on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant Startup
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000318/LER-1993-005-01, :on 931203,found That Main Vent Iodine & Particulate Sampler Pump Not Running.Caused by Lack of self- Checking by Watchstander.Change Will Be Implemented to Replace Current Iodine & Particulate Sampler |
- on 931203,found That Main Vent Iodine & Particulate Sampler Pump Not Running.Caused by Lack of self- Checking by Watchstander.Change Will Be Implemented to Replace Current Iodine & Particulate Sampler
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | 05000317/LER-1993-005, :on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat Exchanger |
- on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat Exchanger
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | 05000317/LER-1993-006, :on 931010,surveillance on Electrical Fire Pump Missed Due to Personnel Error.Pump Declared Inoperable & Missed Surveillance Performed |
- on 931010,surveillance on Electrical Fire Pump Missed Due to Personnel Error.Pump Declared Inoperable & Missed Surveillance Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | 05000317/LER-1993-007-01, :on 931229,performance Test Indicated Possibility of SRW Heat Exchanger Inoperability.Caused by Original Design Calculations Assuming Min SRW Flow Was Not Limiting Case.Hxs Determined Operable |
- on 931229,performance Test Indicated Possibility of SRW Heat Exchanger Inoperability.Caused by Original Design Calculations Assuming Min SRW Flow Was Not Limiting Case.Hxs Determined Operable
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) | 05000317/LER-1993-007, :on 931229,performance Test Indicated Possibilityof SRW HX Inoperability.Caused by Original Design Calculations Assuming Min SRW Flow Was Most Limiting Case. Procedures Revised |
- on 931229,performance Test Indicated Possibilityof SRW HX Inoperability.Caused by Original Design Calculations Assuming Min SRW Flow Was Most Limiting Case. Procedures Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000317/LER-1993-008, :on 931203,determined Removal of EDG Room Shield Door Could Render Other EDGs Inoperable.Caused by Lack of Procedural Controls.Maint Procedure Will Be Generated W/Appropriate Precautions |
- on 931203,determined Removal of EDG Room Shield Door Could Render Other EDGs Inoperable.Caused by Lack of Procedural Controls.Maint Procedure Will Be Generated W/Appropriate Precautions
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) |
|