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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
05000346/LER-1998-003, :on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure1998-06-18018 June 1998
- on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure
05000346/LER-1998-002, :on 980410,plant Tripped Due to High Pressurizer Level as Result of Loss of Letdow Capability. Makeup & Purification Demineralizer 3 Was Isolated Following Trip & Tagged OOS1998-05-10010 May 1998
- on 980410,plant Tripped Due to High Pressurizer Level as Result of Loss of Letdow Capability. Makeup & Purification Demineralizer 3 Was Isolated Following Trip & Tagged OOS
05000346/LER-1997-012, :on 970904,decay Heat Cooler Seismic Design Inadequacy Occurred.Caused by Inadequate Design of Decay Heat Coolers Support Sys.Decay Heat Cooler Mounting Support Sys Will Be re-evaluated & Modified1998-05-10010 May 1998
- on 970904,decay Heat Cooler Seismic Design Inadequacy Occurred.Caused by Inadequate Design of Decay Heat Coolers Support Sys.Decay Heat Cooler Mounting Support Sys Will Be re-evaluated & Modified
05000346/LER-1998-001-02, :on 980407,main Steam Safety Valves Setpoints Were Outside of TS Allowable Values.Cause Will Be Investigated.Setpoint of Valve Adjusted to Be within Allowable Value1998-05-0606 May 1998
- on 980407,main Steam Safety Valves Setpoints Were Outside of TS Allowable Values.Cause Will Be Investigated.Setpoint of Valve Adjusted to Be within Allowable Value
05000346/LER-1997-008, :on 970318,inadequate Testing of Safety Related Logic Was Discovered.Caused by Surveillance Test Review Process Not Technically Detailed Enough to Ensure All Functions Addressed.Performed 18-month Surveillance Test1998-02-25025 February 1998
- on 970318,inadequate Testing of Safety Related Logic Was Discovered.Caused by Surveillance Test Review Process Not Technically Detailed Enough to Ensure All Functions Addressed.Performed 18-month Surveillance Test
05000346/LER-1997-016-01, :on 971217,monthly ECCS Valve Position SR Was Missed.Caused by Flow Path That Was Not Part of Contiguous ECCS Flow Path Envisioned for Compliance W/Ts 4.5.2.Verified Valves Open on 9712221998-01-16016 January 1998
- on 971217,monthly ECCS Valve Position SR Was Missed.Caused by Flow Path That Was Not Part of Contiguous ECCS Flow Path Envisioned for Compliance W/Ts 4.5.2.Verified Valves Open on 971222
05000346/LER-1997-015-01, :on 971212,discovered That EDG Tachometer Circuit Was Outside of 10CFR50 App R Design Basis.Caused by Inadequate Development & Review of Mod 84-0183.Hourly Fire Watch Established & Mod to EDG Tachometer Made1998-01-12012 January 1998
- on 971212,discovered That EDG Tachometer Circuit Was Outside of 10CFR50 App R Design Basis.Caused by Inadequate Development & Review of Mod 84-0183.Hourly Fire Watch Established & Mod to EDG Tachometer Made
05000346/LER-1997-014-01, :on 970801,pressurizer PORV Setpoint Was Less than Allowable Value.Caused by Degraded Wire Splice.Wire Containing Faulty Splice Was Replaced1997-11-26026 November 1997
- on 970801,pressurizer PORV Setpoint Was Less than Allowable Value.Caused by Degraded Wire Splice.Wire Containing Faulty Splice Was Replaced
05000346/LER-1997-013, :on 971002,potential Condition Adverse to Quality Rept Documented Failure to Perform Surveillance Test Before TS Surveillance Late Date.Caused by Administrative Error.Missed Surveillance Completed1997-11-0303 November 1997
- on 971002,potential Condition Adverse to Quality Rept Documented Failure to Perform Surveillance Test Before TS Surveillance Late Date.Caused by Administrative Error.Missed Surveillance Completed
05000346/LER-1996-009, :on 961113,failure to Apply GL 91-18 to EDG Surveillance Testing Occurred.Caused by Personnel Error. Review of GL 91-18 Was Provided to Plant Operations & Plant Engineering Personnel1997-10-24024 October 1997
- on 961113,failure to Apply GL 91-18 to EDG Surveillance Testing Occurred.Caused by Personnel Error. Review of GL 91-18 Was Provided to Plant Operations & Plant Engineering Personnel
05000346/LER-1997-008, :on 970318,inadequate Testing of safety-related Logic Occurred.Caused by Personnel Error.Surveillance Test Was Performed & Completed Satisfactorily W/No Equipment Deficiencies1997-10-23023 October 1997
- on 970318,inadequate Testing of safety-related Logic Occurred.Caused by Personnel Error.Surveillance Test Was Performed & Completed Satisfactorily W/No Equipment Deficiencies
05000346/LER-1997-012, :on 970904,decay Heat Cooler Seismic Design Inadequacy Occurred.Caused by Inadequate Design of Dhc Support Sys.Dhc Mounting Support Sys Will Be re-evaluated1997-10-0606 October 1997
- on 970904,decay Heat Cooler Seismic Design Inadequacy Occurred.Caused by Inadequate Design of Dhc Support Sys.Dhc Mounting Support Sys Will Be re-evaluated
05000346/LER-1997-011, :on 970825,emergency Ventilation Sys Rendered Inoperable by Maint on Room Isolation Valve Occurred.Caused by Misinterpretation of Tech Spec.Preventive Maint Activities Revised1997-10-0202 October 1997
- on 970825,emergency Ventilation Sys Rendered Inoperable by Maint on Room Isolation Valve Occurred.Caused by Misinterpretation of Tech Spec.Preventive Maint Activities Revised
05000346/LER-1997-002-01, :on 970122,identified Potential Overpressurization of Penetrations During Accident Conditions.Installed Mod to Protect Component Cooling Water Supply from Overpressurization Concerns on 9705041997-08-19019 August 1997
- on 970122,identified Potential Overpressurization of Penetrations During Accident Conditions.Installed Mod to Protect Component Cooling Water Supply from Overpressurization Concerns on 970504
05000346/LER-1997-003, :on 970130,potential Condition Adverse to Quality Rept Was Initiated W/Regard to TS Action for Degraded RCS Flow Rate.Caused Because Actions to Reset Affected RPS Trip Setpoints,Not Developed.Guidance Provided1997-08-19019 August 1997
- on 970130,potential Condition Adverse to Quality Rept Was Initiated W/Regard to TS Action for Degraded RCS Flow Rate.Caused Because Actions to Reset Affected RPS Trip Setpoints,Not Developed.Guidance Provided
05000346/LER-1997-008-01, :on 961113,switchboard Circuit Was Declared Inoperable Due to Switchyard Breaker Alignment.Caused by Misunderstanding of Design.Standing Order Was Issued on 961121 to Provide Guidance for Entering TS1997-07-31031 July 1997
- on 961113,switchboard Circuit Was Declared Inoperable Due to Switchyard Breaker Alignment.Caused by Misunderstanding of Design.Standing Order Was Issued on 961121 to Provide Guidance for Entering TS
05000346/LER-1997-007, :on 970305,determined That Acceptance Criteria of Surveillance Test to Measure Leakage Into Dh Valve Pit Potentially non-conservative.Caused by Human Error. Surveillance Test Revised1997-06-20020 June 1997
- on 970305,determined That Acceptance Criteria of Surveillance Test to Measure Leakage Into Dh Valve Pit Potentially non-conservative.Caused by Human Error. Surveillance Test Revised
05000346/LER-1997-008, :on 970318,inadequate Testing of Safety Related Logic Was Identified.Caused by Personnel Error.Testing Was Performed to Verify Equipment Operability1997-06-16016 June 1997
- on 970318,inadequate Testing of Safety Related Logic Was Identified.Caused by Personnel Error.Testing Was Performed to Verify Equipment Operability
05000346/LER-1997-010, :on 970504,Main Transformer Deluge Sys Automatically Actuated Due to Degraded Temp Sensor in Transformer Fire Detection Sys.Replaced Damaged Main Transformer & Sensors That Actuate Deluge Sys1997-06-0303 June 1997
- on 970504,Main Transformer Deluge Sys Automatically Actuated Due to Degraded Temp Sensor in Transformer Fire Detection Sys.Replaced Damaged Main Transformer & Sensors That Actuate Deluge Sys
05000346/LER-1997-006, :on 970225,both Containment Radiation Monitors Were Found to Be Missing Gaskets on Particulate Filter & Iodine Cartridge Holders.Caused by Lack of Procedural Guidance.Missing Gaskets Were Replaced1997-03-27027 March 1997
- on 970225,both Containment Radiation Monitors Were Found to Be Missing Gaskets on Particulate Filter & Iodine Cartridge Holders.Caused by Lack of Procedural Guidance.Missing Gaskets Were Replaced
05000346/LER-1997-005, :on 970212,failed to Perform Surveillance Requirement of Vacuum Leakage Rate Test.Caused by Inadequate Safety Evaluation.Personnel Entered Containment & Verified Kamlock Cover Was Properly Installed1997-03-14014 March 1997
- on 970212,failed to Perform Surveillance Requirement of Vacuum Leakage Rate Test.Caused by Inadequate Safety Evaluation.Personnel Entered Containment & Verified Kamlock Cover Was Properly Installed
05000346/LER-1997-003, :on 970130,non-conservative TS Action for Degraded Reactor Coolant Flow,Occurred Because Calculations Performed in Support of Amend of DBNPS Did Not Consider Need to Adjust Setpoints.Ts Will Be Revised1997-03-0303 March 1997
- on 970130,non-conservative TS Action for Degraded Reactor Coolant Flow,Occurred Because Calculations Performed in Support of Amend of DBNPS Did Not Consider Need to Adjust Setpoints.Ts Will Be Revised
05000346/LER-1997-004, :on 970203,RCP Motor Oil Piping Was Not Protected from Leakage as Required Per 10CFR50 App R.Caused by Personnel Not Realizing Pressurized Piping in Area. Mods Made to Contain Piping as Necessary1997-03-0303 March 1997
- on 970203,RCP Motor Oil Piping Was Not Protected from Leakage as Required Per 10CFR50 App R.Caused by Personnel Not Realizing Pressurized Piping in Area. Mods Made to Contain Piping as Necessary
05000346/LER-1997-002, :on 970122,identified Potential Overpressurization of Penetrations During Accident Conditions.Plant Mods & Procedure Changes Being Developed to Prevent Overpressurization of Piping1997-02-21021 February 1997
- on 970122,identified Potential Overpressurization of Penetrations During Accident Conditions.Plant Mods & Procedure Changes Being Developed to Prevent Overpressurization of Piping
05000346/LER-1997-001, :on 970122,nuclear Instrumentation Declared Inoperable & Incapable of Performing Safety Functions.Caused by Small Shift in Degraded Bottom Linear Amplifier.Power Range Bottom Linear Amplifier Replaced1997-02-21021 February 1997
- on 970122,nuclear Instrumentation Declared Inoperable & Incapable of Performing Safety Functions.Caused by Small Shift in Degraded Bottom Linear Amplifier.Power Range Bottom Linear Amplifier Replaced
05000346/LER-1996-010, :on 961212,CREV Sys Were Not Realized as Inoperable When Radiation Monitors Were Inoperable.Caused by Misinterpretation of Relationship Between Radiation Monitors & Crevs.Standing Order 96-006 Issued1997-01-13013 January 1997
- on 961212,CREV Sys Were Not Realized as Inoperable When Radiation Monitors Were Inoperable.Caused by Misinterpretation of Relationship Between Radiation Monitors & Crevs.Standing Order 96-006 Issued
05000346/LER-1996-008, :on 961113,switchyard Circuit Declared Inoperable Due to Switchyard Breaker Alignment.Ts 3.8.1.1 Entered & Required Breaker Alignment Checks Were Performed1996-12-13013 December 1996
- on 961113,switchyard Circuit Declared Inoperable Due to Switchyard Breaker Alignment.Ts 3.8.1.1 Entered & Required Breaker Alignment Checks Were Performed
05000346/LER-1996-009, :on 961113,failure to Apply Generic Ltr 91-18 Guidance to Emergency Diesel Generator Surveillance Testing Noted.Caused by Lack of Design or Licensing Basis Documentation.Edgs Are Being Revised1996-12-13013 December 1996
- on 961113,failure to Apply Generic Ltr 91-18 Guidance to Emergency Diesel Generator Surveillance Testing Noted.Caused by Lack of Design or Licensing Basis Documentation.Edgs Are Being Revised
05000346/LER-1996-007, :on 961003,CR Emergency Ventilation Sys Design Bases Calculation Error Occurred.Caused by Error in Bechtel Calculation 26.003,CR Pressurization Sys.Cr Boundary Openings Were Verified1996-11-0404 November 1996
- on 961003,CR Emergency Ventilation Sys Design Bases Calculation Error Occurred.Caused by Error in Bechtel Calculation 26.003,CR Pressurization Sys.Cr Boundary Openings Were Verified
05000346/LER-1996-006, :on 960614,discovered High Lip Around Top of Reactor Coolant Pump Motor 2-1 Not in Place.Caused by Inadequate Work Planning.Reactor Coolant Pump Motor Replaced1996-06-13013 June 1996
- on 960614,discovered High Lip Around Top of Reactor Coolant Pump Motor 2-1 Not in Place.Caused by Inadequate Work Planning.Reactor Coolant Pump Motor Replaced
05000346/LER-1996-004, :on 960417,PCAQR 96-0512 Document Failure to Initiate Required Compensatory Actions for Thermo-Lag for Radiant Energy Shields.Caused by Personnel Error.Util Plans to Replace Thermo-Lag1996-05-17017 May 1996
- on 960417,PCAQR 96-0512 Document Failure to Initiate Required Compensatory Actions for Thermo-Lag for Radiant Energy Shields.Caused by Personnel Error.Util Plans to Replace Thermo-Lag
05000346/LER-1996-003, :on 960328,discovered Discrepancy in SRs for Testing of Absorbent Matl in Evs.Caused by Deficiencies in Testing of nuclear-grade Activated Charcoal.Submitted Emergency Amend Request to Revise SRs1996-04-29029 April 1996
- on 960328,discovered Discrepancy in SRs for Testing of Absorbent Matl in Evs.Caused by Deficiencies in Testing of nuclear-grade Activated Charcoal.Submitted Emergency Amend Request to Revise SRs
05000346/LER-1996-002, :on 960320,noted Potential for Loss of Remote Shutdown Capability.Caused by Fire Induced Hot Short Which Could Bypass Valve Protection Features.Implemented Hourly Roving Fire Watches & Completed Evaluations1996-04-19019 April 1996
- on 960320,noted Potential for Loss of Remote Shutdown Capability.Caused by Fire Induced Hot Short Which Could Bypass Valve Protection Features.Implemented Hourly Roving Fire Watches & Completed Evaluations
05000346/LER-1996-001, :on 960304,EECS Inoperable.Caused by Inadequate Safety Review.Plant Mod to Install Manual Vent Valve Will Be Implemented in Tenth Refueling Outage1996-04-0303 April 1996
- on 960304,EECS Inoperable.Caused by Inadequate Safety Review.Plant Mod to Install Manual Vent Valve Will Be Implemented in Tenth Refueling Outage
05000346/LER-1995-003, :on 951117,determined That Removal of Fan C48 from Auxiliary Bldg Radwaste Ventilation Sys on 951006 Inadvertently Rendered Both Trains of SFP Evs Inoperable. Reinstalled Fan C48 on 951118.W/9512181995-12-18018 December 1995
- on 951117,determined That Removal of Fan C48 from Auxiliary Bldg Radwaste Ventilation Sys on 951006 Inadvertently Rendered Both Trains of SFP Evs Inoperable. Reinstalled Fan C48 on 951118.W/951218
05000346/LER-1995-002, :on 950906,discovered Six Post Nuts Missing from Terminal Strip in Cabinet C3629.Caused by Isolated Wiring Error.Terminal Post Nuts Installed on Terminal Strip in Cabinet C36291995-10-0606 October 1995
- on 950906,discovered Six Post Nuts Missing from Terminal Strip in Cabinet C3629.Caused by Isolated Wiring Error.Terminal Post Nuts Installed on Terminal Strip in Cabinet C3629
05000346/LER-1995-001, :on 950126,determined That LOCA Analysis Results for 2 Ft Core Elevation Potentially non-conservative Due to Modeling Errors.Vendor Evaluated Current Fuel Cycle to Determine If Operating Limits Valid1995-02-24024 February 1995
- on 950126,determined That LOCA Analysis Results for 2 Ft Core Elevation Potentially non-conservative Due to Modeling Errors.Vendor Evaluated Current Fuel Cycle to Determine If Operating Limits Valid
1999-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 1999-09-30
[Table view] |
LER-1978-034, /03L-0:on 780326,group 5, Control Rods 11 & 12 Absolute Position Indication Declared Inoperable.Caused Traced to Penetration Area.Updated Rept Will Be Submitted When Exact Cause Determined |
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3461978034R03 - NRC Website |
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text
rm. P unz. s.,y (7 7,C M LICENSEE EVENT REPORT
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CONTROL 8LOCX: l l
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Ih (PLEASE PklNT oR TYl 6L REQUIRED INFORMATIONI 1
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8 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h for Control Rod 12 of Group l The Absciute Position Indication (API)
Ion 2l The API for Control l operable on 3/26/78 at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and on 3/31/78 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />.
rip q l These occurrences l l Rod 11 of Group 5 was declared inoperable on 4/3/78 at 1549 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.893945e-4 months <br />.
[o64l (a) of Technical Specification 3.1.3.3.
There
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(NP-33-78-38) l inoperable during the period that each API was inoperable.
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em TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-78-38 DATE OF EVEUT: March 26, 1978 - April 3, 1978 4
FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Absolute Position Indication (API) for Group 5, Rods 11 and 12 was inoperable.
l 1
The unit was in Modes 1, 2 or 3 with Power (HWT)
. Conditions Prior to Occurrence:
ranging from 0-2336, and Load (MWE) ranging from 0-394.
!~
I Description of Occurrence: On March 26, 1978, the API for Rod 12 of Group 5 was observed to have had sporadic indication.
At 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, this Absolute Position On March 31, 1978, at Indication was declared inoperable by the Shift Foreman.
0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the same API was declared inoperable. On April 3, 1978 at 1549 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.893945e-4 months <br />, the API for Group 5, Rod 11 (displayed on Group 5, Rod 12's position indicating meter) was declared inoperable.
These occurrences placed the unit in Action Statement (a) of Technical Specifica-
~
This Technical Specification requires the operability of all APIS tion 3.1.3.3.
Action Statement (a) of Technical Specification 3.1.3.3 speci-in Modes 1 and 2.
I fies that operation may continue provided that the position reference indicator i
(zone reference) of the control rod is verified within eight hours of the occur-rence, and at least once per twelve hours thereafter.
i l
In each case, Group 5 was placed in the asymmetric bypass condition.
I Although the exact cause of these Designation of Apoarent Cause of Occurrence:
occurrences is not yet known, the problem has been traced to the penetration When the cause is known, an updated report will be submitt'ed.
area.
4 There was no-danger to the health and safety of the Analysis of Occurrence:
The Relative Position Indication (RFI) as well as public or to unit personnel.
zone reference indication for each rod was operable during the period that each 1.
j API was inoperable.
Surveillance requirements 4.1.3.3 as well as the requirements Corrective' Action:
of Action Statement (a) was followed.
As reported in Licensee Event Report NP-33-78-26, Maintenance personnel performed an inspection of connectors and cable at the bulkhead, control rod drive =echanism, and position indicator tube for Control Rod Drive Group 5 Rod 12 under Maintenance Since Licensee Event Report NP-33-78-26 was written, Work Order (11WO)78-319.
LER 67S-034
~-
, m.
i TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR ' POWER STATION I
SUPPLEMENTAL INFORMATION FOR LER NP-33-78-38
. PAGE]
4 Maintenanc,e has replaced the cable from the API tube to the bulkhead ()NO 78-512).
i NNO 718-78 was issued (af ter approval of Facility Change Request 78-169) to i
change wires at the penetration from Rod 12 to a spara and to switch the position indication cables for Rods 11 and 12 at the position indication tubes. The posi-t tion indication patch for Rods 11 and 12 were exchanged under MWO IC 277-78. On March 30, 1978, the patch and position cables were returned to their original con-i.
figuration.
On March 31, 1978, under Facility Change Request (FCR)78-173, the position indi-cation cable for Group 5 Rod 12 was switched with the position indication cable 4
l for Group 5 Rod 11.
In addition, the cable for Group 5 Rod 12 from the penetration to the bulkhead was replaced with a new one. All work was performed under MWO 78-512. This change was recommended by Diamond Power Specialty Corporation as an aid in cr,oubleshooting the Group 5 Rod 12 problem. As a result of this change, the API signal for Group 5 Rod 12 was on Group 5 Rod 11s API meter and vice versa.
Relative Position Indication for each rod remained unaffected. The zone reference lights for Group 5 Rod 12 were displayed on Group 5 Rod ils zone reference lights, and vice versa.
1 On April 7, 1978 under FCR 78-180 and ISO IC 285-78, the API signal leads for Group 5 Rod 11 were exchanged with the API signal leads for Group 5 Rod 12 at the 1
' penetration. The APIS for both Rod 11 and 12 of Group 5 were inoperable for the few minutes required to switch cables.
RPIs and zona reference lights for each rod were operable during this time. The API signals for Group 5 Rods 11 and 12 I
were returned to their respective meters. The zone reference lights for Rod 12 of Group 5 were still displayed on Rod 11 Group 5s zone reference lights. As a result of this change, it was determined that the problem with the API on Rod 12
]
of Group 5 originated in the penetration area.
~
The unit was removed from Action Statement (a) of Technical Specification 3.1.3.3 on March 30,1978 at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, on March 31, 1978 at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> and on April 6, 1978 at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, af ter performance of Surveillance Test ST 5013.03, "Contain-ment Pressure to SEAS Channel Calibration".
j Absolute Position Indication for Group 5 Rod 12 (on ll, 5s API meter) remains inoperable as of April 19, 1978.
Due to high radiation levels inside containment during.present power operation, further investigation in the penetration area has been scheduled for the next outage. Also during this time, position indication ' ables for Group 5, Rods 11 c
and 12 will be returned to these original rods.
Failure Data:.The API for Rod 12, Group 5 was inoperable in three previously reported. occurrences, Li:ensee Event Reports NP-33r78-02, NP-33-78-19 and
,,,s NP-13-7S-26.
7 tis is a repetitive occurrence but the cause has not yet been
[
t I
determined.
i LIK #78-034
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05000346/LER-1978-002-03, /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | | 05000346/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | 05000346/LER-1978-003-03, /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | | 05000346/LER-1978-003, Forwards LER 78-003/03L-0 | Forwards LER 78-003/03L-0 | | 05000346/LER-1978-004, Forwards LER 78-004/03L-0 | Forwards LER 78-004/03L-0 | | 05000346/LER-1978-004-03, /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | | 05000346/LER-1978-005-03, /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | | 05000346/LER-1978-005, Forwards LER 78-005/03L-0 | Forwards LER 78-005/03L-0 | | 05000346/LER-1978-006-03, /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | | 05000346/LER-1978-006, Forwards LER 78-006/03L-0 | Forwards LER 78-006/03L-0 | | 05000346/LER-1978-007-03, /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | | 05000346/LER-1978-007, Forwards LER 78-007/03L-0 | Forwards LER 78-007/03L-0 | | 05000346/LER-1978-008-03, /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | | 05000346/LER-1978-008, Forwards LER 78-008/03L-0 | Forwards LER 78-008/03L-0 | | 05000346/LER-1978-009-03, /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | | 05000346/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | 05000346/LER-1978-010-03, /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | | 05000346/LER-1978-010, Forwards LER 78-010/O3L-0 | Forwards LER 78-010/O3L-0 | | 05000346/LER-1978-011, Forwards LER 78-011/03L-0 | Forwards LER 78-011/03L-0 | | 05000346/LER-1978-011-03, /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | | 05000346/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | 05000346/LER-1978-012-03, /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | | 05000346/LER-1978-013-03, /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | | 05000346/LER-1978-013, Forwards LER 78-013/03L-0 | Forwards LER 78-013/03L-0 | | 05000346/LER-1978-014, Forwards LER 78-014/03L-0 | Forwards LER 78-014/03L-0 | | 05000346/LER-1978-014-03, /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | | 05000346/LER-1978-015, Forwards LER 78-015/03L-0 | Forwards LER 78-015/03L-0 | | 05000346/LER-1978-015-03, /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | | 05000346/LER-1978-016-03, /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | | 05000346/LER-1978-016, Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | | 05000346/LER-1978-017, Forwards LER 78-017/03L-0 | Forwards LER 78-017/03L-0 | | 05000346/LER-1978-017-03, /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | | 05000346/LER-1978-018-03, /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | | 05000346/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | | 05000346/LER-1978-019-03, /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | | 05000346/LER-1978-020, Forwards LER 78-020/03L-0 | Forwards LER 78-020/03L-0 | | 05000346/LER-1978-020-03, /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | | 05000346/LER-1978-021-03, /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | | 05000346/LER-1978-022-03, /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | | 05000346/LER-1978-022, Forwards LER 78-022/03L-0 | Forwards LER 78-022/03L-0 | | 05000346/LER-1978-023-03, /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | | 05000346/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | 05000346/LER-1978-024-03, /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | | 05000346/LER-1978-025-03, /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | | 05000346/LER-1978-025, Forwards LER 78-025/03L-0 | Forwards LER 78-025/03L-0 | | 05000346/LER-1978-026, Forwards LER 78-026/03L-0 | Forwards LER 78-026/03L-0 | | 05000346/LER-1978-026-03, /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | | 05000346/LER-1978-027, Forwards LER 78-027/03L-0 | Forwards LER 78-027/03L-0 | | 05000346/LER-1978-027-03, /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque | /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque Out | | 05000346/LER-1978-028-03, /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | |
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