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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-1999-005, :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-1998-005-01, :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-1998-004-01, :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-1998-003-01, :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
05000317/LER-1995-002-01, :on 950616,manual Trip Occurred Due to Loss of 12 SG Feed Pump.Repaired Overspeed Trip Mechanism & Restarted Unit 11995-07-14014 July 1995
- on 950616,manual Trip Occurred Due to Loss of 12 SG Feed Pump.Repaired Overspeed Trip Mechanism & Restarted Unit 1
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 ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr 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
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 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors 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 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
ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with 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
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 ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With 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 ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves 1999-09-30
[Table view] |
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e.
B A LTIMORE GAS AND ELECTRIC CALVERT CLIFFS NUCLEAR POWER PLANT 1650 CALVERT CLIFFS P ARKWAY
- LUSBY. MARYLAND 20657-4702 CHARLES H. CAUSE PLANT GENERAL '.tANAC,ER March 9, 1993 cavERr et rrs U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
Document Control Desk
SUBJECT:
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 93-001 Technical Specification 3.0.3 Entry; Loss of Control Room Air Conditioninc 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
'Q S u > f,C f CHC/RCG/bj d Attachment cc:
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 I
170041 i
9303170090 930309 PDR ADOCK 05000317 7AM S
pga 1]/ ~
1
e "O
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSON H2)
ESTlMATO RURODJ PG TSF@EE To COMFLYWITHTO MoreATON COLLECTION EoVEST: 300 HR1 FORNAFO COMMENTS TMtwo L1CENSEE EVENT REPORT (LER)
BNNTE TW MNTOMO REMOS MWGEMENT EFWCH IBMlB 7714), US NUCLEAR E<,tAATOFN CCMMISSOM WASFWGTOM DC2065MX101. ANDToTKPAPE7WOf4GEI)UCTONPralECT (See reverse for reauired numt er of gjgits/ characters for each block)
NN#EN "EMNN FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Calvert Cliff s, Unit 1 05000 317 1 OF 08 TITLE (4)
Technical Specification 3.0.3 Entry; Loss of Control Room Air Conditioning EVENT DATE (5)
I LER NUMSER (6)
REPORT DATE m oTHER FAC:LITIES INVOLVED de)
YEARfYEAR S
N MONTH DAY MONTH DAY YEAR NUMBER NUMBER Calvert Cliffs U2 05000 318 02 02 93 93
-- 001 00 03 09 93 05000 OPERATING THIS REPORT IS SUBMtTTED PURSU4NT TO THE REQUIREVENTS OF 10 CFR -!Chnclr one or mcwe) fit)
I MODE (9) j 20.402(b) 20.405(c) l
{ 5013(a)m(M 73 71(b) l 20 405(a)(1)(1) 50.36(c)(1) l l 50.73(a)m(v)
T311(c) p LEVEL 100 120.40swm60 50.aste)m
! M 73(e)m(vii) gg 00)
" 20.405(a)(1)(W)
X SoJ3(a)(2)(t) 50 73(a)m(voi)(A)
(Speafy in Abstrad beeow and in.
Text. NRC Form 366A) 20.405(a)(1)(M 50J3(a)m(10 5033(alm (viiO(U) 20 405fa)(1)M 50 73(a)m(iii) 5033(a)mM LICENSEE CONTACT FoR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Code)
R, C. Gradle, Compliance Engineer 410-260-3738 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRIBED IN THIS REPORT (13)
- 0' CAUSE SYSTEM CouPONENT
CAUSE
l SYSTEMCOMPONEMT l
TURER NPRDS TURER NPRDS l
SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED M ONTH DAY YEAR l YES X
No SUBMISSION l
'tf ves comrAete EYPECTED SUButSSloN DATE)
DATE (15) i ABSTRACT (Uma to 1400 spaces, i e., appronjrnatory15 sangespace typewntren knes) (16)
On February 2, 1993, at 9:55 a.m., both independent Control Room Emergency Ventilation System Air Conditioning trains (CR HVACs) were declared inoperable at Calvert Cliffs and the plant entered Technical Specification 3.0.3.
The No. 12 CR HVAC train was determined to be inoperable while No. 11 CR HVAC s
train was removed from service for scheduled routine maintenance.
Immediate action restored No. 11 CR HVAC train to OPERABLE status at 10:30 a.m.,
35 minutes after the start of the event.
At the time of the event Units 1 and 2 were at 100 percent power.
The immediate cause of No, 12 CR HVAC being inoperable was determined to be insufficient system refrigerant inventory.
This event did not result in any significant safety consequences.
Immediate corrective actions included charging No. 12 CR HVAC with additional refrigerant, performing appropriate surveillance testing and restoring it to an OPERA 3LE status on February 3, 1993.
'Je are performing a detailed design review of the CR HVAC system to define guidelines for system refrigerant inventory requirements under design outdoor air temperature conditions.
rec Fam me se
l JU.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150 4104 dWm EXPIRES 5/31/95 ESTrMATED BUFOEN PER RESPONSE TD COMPLY WITH THIS INFoRMATON CouECTON REcuCST: 50 0 HRS. FORWARD LJCENSEE EVENT REPORT (LER) couutWTs REcARono suRoEN tswATs to TxE woRuATON ANo RECORDS MANAGEMENT BRANCH (MNBB Ute). MS NUCLEAR a
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LER NUMBER p)
PAGE H)
Calvert Cliffs, Unit 1 05000 3 1 7 93 001 -
00 02 0F 08 TEXT s c.... m oa.aamo m o NRcr asam cm I.
DESCRIPTION OF EVENT
On February 2, 1993, at 9:55 a.m., both independent Control Room Emergency Ventilation System Air Conditioning trains (HVACs) were declared inoperable at Calvert Cliffs.
The No. 12 CR HVAC train was determined to be inoperable while No. 11 CR HVAC train was removed from service for scheduled routine maintenance.
Since there is no ACTION requirement for both Control Room (CR) HVAC trains being inoperable, the plant entered Technical Specification (TS) 3.0.3.
Immediate corrective action restored No. 11 CR HVAC train to OPERABLE status at 10:30 a.m.,
35 minutes after the start of the event. At the time of the event both Units were at 100 percent power.
Calvert Cliffs has a single Control Room from which both Unit 1 and Unit 2 operations are conducted. The CR Emergency Ventilation System consists of two independent and redundant CR HVAC trains.
The air conditioning units are field installed customized units. Detailed design and as-built technical manual information does not exist for these units.
Each CR HVAC train has an individual source of outside air and draws on the common exhaust header for recirculation air.
Normally, one CR HVAC train is in operation with the other train in standby.
Each CR HVAC train has an air handling unit, evaporator, liquid receiver, air-cooled condenser, compressor, and a head pressure control system that permits operation during low outdoor air temperatures (Figure 1).
Low ambient temperature operation prevents excessive heat rejection capacity in the air-cooled condenser and the condenser backpressure regulating valve closes allowing liquid refrigerant to backup or " stack" in the condenser coils. To maintain adequate compressor suction pressure, a condenser bypass regulating valve opens bypassing hot refrigerant gas directly to the receiver.
1 On January 30, 1993, we completed an approved modification to No. 12 CR HVAC head pressure control system (the modification is not currently installed on No.
11 CR HVAC train).
The modification, in part, increased the size of the hot gas bypass line and its condenser bypass regulating valve, providing higher hot gas flow during low ambient temperature operations.
During the restoration of the train, utility refrigeration mechanics recharged the original inventoried amount of refrigerant, approximately 700 pounds, back into the system.
The maximum total refrigerant inventory is limited by design to 30 percent receiver capacity (approximately 800 pounds of refrigerant). The train was then started and run continuously for a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as required by established plant procedures.
The train passed its post modification test and was declared
NRC FCRM 366A -
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f ACIUTV 86AME (1)
DOCKET NUMBER (a t.ER NUut1R (3 PAGE(4 i
Calvert Cliffs, Unit 1 05000 3 1 7 93 001 -
00 03 0F 08 i
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operable.
Outside temperature during the post-modification testing did not fall below 25 degrees Fahrenheit.
i At approximately 5:00 a.m., on February 2,1993, a licensed Control Room Operator (CRO) stopped No. 11 and started No. 12 CR HVAC. At 5:25 a.m. No. 11-CR HVAC was removed from service for scheduled inspections and preventative maintenance.
i
+
While attempting to tag out No, 11 compressor, plant Safety Tagging personnel had difficultly racking out its supply breaker (No. 52-1108).
Investigation by Electrical Maintenance personnel found metal shavings on the bottom of the t
breaker cabinet.
The breaker was removed from its cabinet and transported to
~
the Electrical Maintenance Shop. Troubleshooting efforts found the breaker levering (racking) mechanism was binding.
At approximately 7:30 a.m.,
Control Room personnel observed increasing Control Room air temperatures and proceeded to open outside air dampers to reduce temperatures. The Unit 1 Auxiliary Building operator (ABO) was dispatched to check No. 12 CR HVAC compressor. The A30 later reported that the compressor was not running. At this point, unsure of the status of the 12 CR HVAC train, Operators contacted the responsible System Engineer.
t At approximately 8:00 a.m.,
the System Engineer and Mechanical Maintenance personnel arrived to assist Operations personnel investigate the compressor problem.
Following approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of troubleshooting activity and operability evaluation No. 12 CR HVAC was declared inoperable at 9:55 a.m. and, i
TS 3.0.3 was entered.
During the course of their evaluation they determined l
refrigerant inventory was low noting that the receiver level gauge read low, there was indication of bubbling in the receiver level gauge, and compressor suction pressure was low.
Due to the unusually cold outside air temperature j
(about 16 degrees Fahrenheit) they concluded the condenser was stacked with liquid refrigerant.
Insufficient refrigerant inventory in the receiver induced the low suction pressure at the compressor. They concluded the compressor had i
tripped on low suction pressure durinS its attempted starting.
Suction pressure was not rising to reset the low suction pressure trip.
3reaker 52-2408, which is identical to Breaker No. 52-1108, was installed in the cubicle for breaker No. 52-1108, 11 CR HVAC train was started, run, and declared OPERA 3LE at 10:30 a.m. and TS 3.0.3 was exited.
Corrective actions were then begun to return No. 12 CR HVAC train to an operable i
status and to identify the causes of each inoperability.
i n- -.
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CAUSE OF EVENT
The immediate cause of No. 12 compressor becoming inoperable was insufficient refrigerant level to support a compressor start at extremely low outside r
temperatures.
During cold outdoor temperature conditions, sufficient t
refrigerant inventory must be maintained in the air conditioning unit to compensate for density changes and stacking of liquid refrigerant in the condenser while maintaining adequate refrigerant inventory in the receiver.
Insufficient refrigerant in the receiver can induce a low compressor suction pressure resulting in a compressor trip during starting. At the time of the event, outside air temperature was approximately 16 degrees Fahrenheit. This caused a significant amount of refrigerant to migrate to the condenser resulting in a low suction pressure at the compressor.
Factors that contributed to the insufficient refrigerant level are as follows:
A.
The relationship between required refrigerant inventory and outside air i
temperature was not quantitatively known for the air conditioning units.
1 We understood a relationship did exist between refrigerant inventory, outside air temperature and compressor suction pressure, but no detailed calculations existed quantifying this relationship.
Due to the fact that these are customized field installed units, the vendor manual did not address their actual design parameters (i.e., inventory and design operating condition relationships) i B.
The procedures for recharging an air conditioning unit did not clearly specify how to determine the amount of refrigerant required in the system.
+
Troubleshooting of 3reaker 52-1108 revealed that the spacer bushing behind the racking (drive) bolt of the levering mechanism had been vorn down.
The breaker i
had never been rebuilt. The spacer bushing wear allowed axial movement of the threaded portion of the worm gear drive shaft which bound up with the rear l
bearing surface. This binding occurred when the breaker was being racked in the out direction only.
The defective leverin5 mechanism did not adversely affect the breakers ability to function when installed in its cubicle.
No other levering mechanism failures with a similar failure mode have been observed in the-past.
III.
ANALYSIS OF EVENT
The two trains of the Control Room Emergency Ventilation System provide redundant capability for cooling and filtering of Control Room air. The system
.U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 315o-01o4 p.s2; EXPIRES 5/31/95 ESTNATED BUFDE N PER RESPONSE To CoM8'LY WITH THIS
- oFNATON CoufCTON R6oVEST: E0 HFR FORWARD LICENSEE EVENT REPORT (LER)
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Calvert Cliffs, Unit 1 05000 3 1 7 93 001 -
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,. u
. --.aa= =, nRC F.,,n saw nn is designed to ensure equipment operability and habitability in the Control Room during and following all credible accident conditions. Air circulation through the Control Room was never affected and environmental conditions remained within design limits during the event.
The plant is equipped with the means to achieve safe shutdown should it be required in the event of inadequate Control Room cooling. A loss of the Control Room Emergency Ventilation System requires immediate shutdown to MODE 5 (Cold Shutdown) per plant Technical Specifications. During the period when both CR HVAC trains were inoperable, in the unlikely event of a loss of coolant accident with subsequent core damage, Control Room Operators may have been required to initiate outside air ventilation to maintain Control Room temperatures below design requirements.
These actions could have increased Operator dose above established limits, but the potential to achieve a safe shutdown would not have been threatened. Most scenarios would have afforded adequate time to restore a train of HVAC equipment to avoid such potential dose consequences.
This event is considered reportable in accordance with 10 CFR 50.73(a)(2)(1)(3),
"Any operation or condition prohibited by the plant's Technical Specifications."
The total duration of the event was 35 minutes.
IV.
CORRECTIVE ACTIONS
Immediate A.
No. 12 CR HVAC compressor breaker was installed and tested in the cubicle for No. 11 CR HVAC compressor breaker.
No. 11 CR air conditioner unit was verified as loading and operating satisfactorily and 11 CR HVAC was declared OPERABLE at 10:30 a.m. on February 2.
3.
The levering mechanism was replaced in breaker No. 52-1108 and the breaker was operationally tested to ensure no mechanism binding.
Electrical resistance checks were performed satisfactorily. Electrical Maintenance personnel coordinated with Operations personnel and breaker No. 52-1108 was racked smoothly into the breaker cubicle 52-2408 for No. 12 CR HVAC l
compressor on February 2 at approximately 7:30 p.m.
C.
A detailed troubleshooting procedure was initiated for No. 12 CR HVAC.
The system was charged with 100 pounds of additional refrigerant. At 3:4 5 p. :n. on February 2, 1993, No. 12 CR HVAC train was started and successfully operated during a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test.
The train was then shutdown and allowed to cooldown in preparation for a planned cold start
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.U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104
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The surveillance test was commenced at 1:48 a.m. on February 3 and concluded at 2:45 p.m. that same day.
No. 12 CR HVAC was declared OPERABLE at 2:45 p.m on February 3.
Actions to Prevent Recurrence:
A.
Design Engineering is performing a detailed review of the relationship between required refrigerant inventory and outside air temperature.
This relationship is needed to define guidelines between recommended refrigerant inventory and outside air temperature for our CR HVAC system.
7 This information will be utilized in subsequent maintenance activities to ensure the system meets full system design requirements.
3.
Procedures for maintenance of the CR HVAC systems will be revised to ensure they specify an appropriate weight of refrigerant.
C.
Based upon the guidelines from Design Engineering, we will evaluate methods to ensure that adequate refrigerant inventory is maintained for CR I
HVAC system operation.
l D.
Operating practices are being modified to additionally record, at appropriate intervals, the receiver liquid level of the standby CR HVAC train.
)
V.
ADDITIONAL INFORMATION
l 1
A.
Table of Components and Systems Receiving Mention in this LER.
I IEEE 803A/83 IEEE 805/84 Component or System Funct. Ident.
System Code CR HVAC ACU VI Compressor CMP j
Receiver RCV Condenser COND I
Breaker 3KR Evaporator EVP 1
I I
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Previous Similar Events
There has been one previous similar event involving an entry into TS 3.0.3 caused by a loss of CR HVAC (LER 318/91-006).
This event occurred because procedural guidance was not sufficient to prevent non-condensible gasses from being introduced into the system. This resulted in a reduced air conditioning efficiency that interfered with the systems ability to rej ect heat during hot days.
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F ACIUTv NAME (1)
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PAGE(4)
Calvert Cliffs, Unit 1 05000 3 1 7 93 001 00 08 0F 08 i
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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) |
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