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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000361/LER-1999-005-01, :on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 9908311999-09-23023 September 1999
- on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 990831
05000206/LER-1999-001-02, :on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension1999-08-31031 August 1999
- on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension
05000361/LER-1999-004-01, :on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired1999-08-0606 August 1999
- on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired
05000362/LER-1999-005, :on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With1999-07-28028 July 1999
- on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With
05000362/LER-1999-006, :on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With1999-07-26026 July 1999
- on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With
05000362/LER-1999-003-01, :on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced1999-06-11011 June 1999
- on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced
05000362/LER-1999-004, :on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced1999-06-11011 June 1999
- on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced
05000362/LER-1999-002-01, :on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With1999-05-20020 May 1999
- on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With
05000362/LER-1999-001-01, :on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With1999-03-12012 March 1999
- on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With
05000361/LER-1999-002, :on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With1999-03-10010 March 1999
- on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With
05000361/LER-1999-001, :on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with1999-03-0303 March 1999
- on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with
05000361/LER-1998-021, :on 980903,train B Ecw Chiller Failed to Start Using CR Start Push Button.Caused by Incorrect Wiring of Switch by Personnel.Wiring Was Corrected & Chiller Was Declared Operable on 9809261998-10-26026 October 1998
- on 980903,train B Ecw Chiller Failed to Start Using CR Start Push Button.Caused by Incorrect Wiring of Switch by Personnel.Wiring Was Corrected & Chiller Was Declared Operable on 980926
05000361/LER-1998-020, :on 980806,determined That Ecw Sys Was Inoperable.Caused by Faulty Temp Control Unit.Temp Control Unit Was Replaced & Chiller Performed Satisfactorily1998-10-26026 October 1998
- on 980806,determined That Ecw Sys Was Inoperable.Caused by Faulty Temp Control Unit.Temp Control Unit Was Replaced & Chiller Performed Satisfactorily
05000361/LER-1998-004-01, :on 980211,diesel Fuel Oil Particulates - ASTM Test Methods Yield Varying Results Were Received.Caused by Unexpected Variations Obtained from Different Test Methods. Fuel Oil Filtered & Confirmed by Reanalysis1998-09-0101 September 1998
- on 980211,diesel Fuel Oil Particulates - ASTM Test Methods Yield Varying Results Were Received.Caused by Unexpected Variations Obtained from Different Test Methods. Fuel Oil Filtered & Confirmed by Reanalysis
05000361/LER-1998-011, :on 980617,determined That Setpoints for High Log Power Bypass Automatic Removal Had Not Been Verified IAW Ts.Caused by Log Power Not Satisfying TS as Written.Utils Investigation If Ongoing & LER Will Be Revised by 9809301998-07-17017 July 1998
- on 980617,determined That Setpoints for High Log Power Bypass Automatic Removal Had Not Been Verified IAW Ts.Caused by Log Power Not Satisfying TS as Written.Utils Investigation If Ongoing & LER Will Be Revised by 980930
05000206/LER-1998-004, :on 980323,safeguards Drawing Was Inappropriately Decontrolled.Caused by Personnel Error. Revised Procedure for Decontrolling SI & Has Established New Detailed Process for SCE to More Effectively Control SI1998-07-10010 July 1998
- on 980323,safeguards Drawing Was Inappropriately Decontrolled.Caused by Personnel Error. Revised Procedure for Decontrolling SI & Has Established New Detailed Process for SCE to More Effectively Control SI
05000361/LER-1996-012, :on 960226,condensate Storage Tank Outside Design Basis Occurred.Caused by Several Mechanisms for Loss of Water Vol from T-120.Procedures Revised1998-06-29029 June 1998
- on 960226,condensate Storage Tank Outside Design Basis Occurred.Caused by Several Mechanisms for Loss of Water Vol from T-120.Procedures Revised
05000361/LER-1998-009, :on 980428,discovered That Steps in Aoi to Isolate Tank Following Operating Bases Earthquake Had Been Inadvertently Deleted in Aug 1996.Caused by Individual Error.Event Reviewed W/Individual Involved1998-06-29029 June 1998
- on 980428,discovered That Steps in Aoi to Isolate Tank Following Operating Bases Earthquake Had Been Inadvertently Deleted in Aug 1996.Caused by Individual Error.Event Reviewed W/Individual Involved
05000361/LER-1998-010, :on 980526,post-accident Cleanup Units Trains Were Declared Inoperable.Unit Concluded Condition May Be Reportable Under 10CFR50.73(a)(2)(i) for Operation During Past Refueling Outages.Ler Will Be Revised by 9808281998-06-29029 June 1998
- on 980526,post-accident Cleanup Units Trains Were Declared Inoperable.Unit Concluded Condition May Be Reportable Under 10CFR50.73(a)(2)(i) for Operation During Past Refueling Outages.Ler Will Be Revised by 980828
05000361/LER-1986-036, :on 860619,line Voltage Regulators Caused Vital Buses to Be Inoperable.Caused by Procedural Discrepancy. Revised Procedure SO23-II-11.1841998-06-0606 June 1998
- on 860619,line Voltage Regulators Caused Vital Buses to Be Inoperable.Caused by Procedural Discrepancy. Revised Procedure SO23-II-11.184
05000361/LER-1996-012, :on 960229,discovered That CST Was Outside Design Basis.Cause Under Investigation.Compensatory Measures Were Put in Place to Administratively Increase Tanks Water Volume & to Procedularize Operator Actions1998-05-29029 May 1998
- on 960229,discovered That CST Was Outside Design Basis.Cause Under Investigation.Compensatory Measures Were Put in Place to Administratively Increase Tanks Water Volume & to Procedularize Operator Actions
05000361/LER-1998-009, :on 980429,discovered That CST Was Outside Design Basis Due to Procedure Error.Caused by Individual Error.Replaced Steps That Had Been Inadvertently Deleted from Aoi1998-05-29029 May 1998
- on 980429,discovered That CST Was Outside Design Basis Due to Procedure Error.Caused by Individual Error.Replaced Steps That Had Been Inadvertently Deleted from Aoi
05000361/LER-1998-003, :on 980205,inoperable Valve Occurred Due to Grit in Linestarter Mechanism.Sce Has Been Programmatically Replacing Square D Linestarters1998-04-17017 April 1998
- on 980205,inoperable Valve Occurred Due to Grit in Linestarter Mechanism.Sce Has Been Programmatically Replacing Square D Linestarters
05000361/LER-1998-001, :on 980113,loose Collar Was Noted on Turbine Driven AFW Speed Circuit.Caused by Collar Not Properly Being Tightened at Last Documented Reassembly in 1993.Collar & Plug Were Reassembled1998-04-17017 April 1998
- on 980113,loose Collar Was Noted on Turbine Driven AFW Speed Circuit.Caused by Collar Not Properly Being Tightened at Last Documented Reassembly in 1993.Collar & Plug Were Reassembled
05000361/LER-1998-007, :on 980317,discovered Matl in Containment That Could Become Debris in Emergency Sumps.Caused by Ineffective Program Mgt.Removed Identified Matl & Will Issue Memo to Personnel Emphasizing Containment Cleanliness Maint1998-04-16016 April 1998
- on 980317,discovered Matl in Containment That Could Become Debris in Emergency Sumps.Caused by Ineffective Program Mgt.Removed Identified Matl & Will Issue Memo to Personnel Emphasizing Containment Cleanliness Maint
05000206/LER-1998-003-01, :on 980316,unauthorized Protected Entry Area Entry,Was Determined.Caused by Data Entry Error.Appropriate Collection Site Personnel Were Coached.Computer Data Base Modified1998-04-0808 April 1998
- on 980316,unauthorized Protected Entry Area Entry,Was Determined.Caused by Data Entry Error.Appropriate Collection Site Personnel Were Coached.Computer Data Base Modified
05000361/LER-1998-005, :on 980305,inadequate Voltage to 120 Vac Circuits Due to Calculation Error Occurred.Caused by Personnel Error.Sys Mods Made to Affected Sys to Correct Deficiencies1998-04-0606 April 1998
- on 980305,inadequate Voltage to 120 Vac Circuits Due to Calculation Error Occurred.Caused by Personnel Error.Sys Mods Made to Affected Sys to Correct Deficiencies
05000361/LER-1998-008, :on 980306,4160 Vac Supply Cable Exceeded Ampacity Rating.Caused by Error in Feeder Cable Sizing Calculation Completed by Plant Architect/Engineer. Administrative Restrictions Imposed1998-04-0606 April 1998
- on 980306,4160 Vac Supply Cable Exceeded Ampacity Rating.Caused by Error in Feeder Cable Sizing Calculation Completed by Plant Architect/Engineer. Administrative Restrictions Imposed
05000206/LER-1998-002-01, :on 980219,diesel Fuel Filtration Unit Access Was Not Controlled as Vital Area.Caused by Inadequate Training.Security Personnel Will Be Trained on Concept of Vital Matls1998-03-20020 March 1998
- on 980219,diesel Fuel Filtration Unit Access Was Not Controlled as Vital Area.Caused by Inadequate Training.Security Personnel Will Be Trained on Concept of Vital Matls
05000362/LER-1984-045-01, :on 840719,recognized That Four Iodine Transients Met Reporting Criteria of TS 3.4.7,but Had Not Been Reported.Cause Indeterminate.Nrc Approved TS Amend Which Deleted Reporting Requirement of TS 3.4.7.A1998-03-0303 March 1998
- on 840719,recognized That Four Iodine Transients Met Reporting Criteria of TS 3.4.7,but Had Not Been Reported.Cause Indeterminate.Nrc Approved TS Amend Which Deleted Reporting Requirement of TS 3.4.7.A
05000361/LER-1998-002, :on 980126,reactor Coolant Sys Boundary Leakage Occurred.Caused by Cracking of Inconel 600 Nozzle.Four Nozzles (2TW0139B,2TE0122-4,2PDT0978-1 & 2PDT0978-2) Were Repaired1998-02-25025 February 1998
- on 980126,reactor Coolant Sys Boundary Leakage Occurred.Caused by Cracking of Inconel 600 Nozzle.Four Nozzles (2TW0139B,2TE0122-4,2PDT0978-1 & 2PDT0978-2) Were Repaired
05000361/LER-1998-001-01, :on 980113,turbine Driven Auxiliary Feedwater Pump Speed Circuit Collar Loose Were Noted.Caused by vibration-induced Loosening During Periodic Pump Test Runs. Collar & Plug Were Reassembled1998-02-12012 February 1998
- on 980113,turbine Driven Auxiliary Feedwater Pump Speed Circuit Collar Loose Were Noted.Caused by vibration-induced Loosening During Periodic Pump Test Runs. Collar & Plug Were Reassembled
05000362/LER-1997-003-02, :on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel1998-01-19019 January 1998
- on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel
05000362/LER-1997-004-01, :on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-1541998-01-0505 January 1998
- on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-154
05000361/LER-1997-016, :on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel1998-01-0202 January 1998
- on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel
05000206/LER-1997-003-01, :on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored1997-12-22022 December 1997
- on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored
05000206/LER-1997-002-02, :on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation1997-11-25025 November 1997
- on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation
05000361/LER-1997-011, :on 970704,instrumentation Channel 1 Declared Inoperable.Caused by Cognitive Personnel Error.Operator Was Coached in Need for Attention to Detail & Util Revised Procedures1997-08-0505 August 1997
- on 970704,instrumentation Channel 1 Declared Inoperable.Caused by Cognitive Personnel Error.Operator Was Coached in Need for Attention to Detail & Util Revised Procedures
05000361/LER-1997-011, :on 970704,wrong B Sample Was Used for Shutdown Margin Surveillance.Caused by Personnel Error.Revised Procedures for Performing SDM Calculations1997-07-30030 July 1997
- on 970704,wrong B Sample Was Used for Shutdown Margin Surveillance.Caused by Personnel Error.Revised Procedures for Performing SDM Calculations
05000362/LER-1997-002-01, :on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl1997-07-30030 July 1997
- on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl
05000361/LER-1997-010, :on 970626,check Valve in Charging Subsystem Failed to Open Completely.Caused by Design Defect.Replaced Faulty Design Valves.Rept Includes 10CFR21 Info1997-07-28028 July 1997
- on 970626,check Valve in Charging Subsystem Failed to Open Completely.Caused by Design Defect.Replaced Faulty Design Valves.Rept Includes 10CFR21 Info
05000361/LER-1997-009, :on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases1997-06-0505 June 1997
- on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases
05000362/LER-1997-001-02, :on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding1997-05-0909 May 1997
- on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding
05000361/LER-1997-006, :on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised1997-04-18018 April 1997
- on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised
05000361/LER-1997-008, :on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated1997-04-18018 April 1997
- on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated
05000361/LER-1997-005, :on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth1997-04-15015 April 1997
- on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth
05000361/LER-1997-004, :on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 6901997-04-0202 April 1997
- on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 690
05000361/LER-1997-003, :on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis1997-03-18018 March 1997
- on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis
05000361/LER-1997-002, :on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt1997-03-0707 March 1997
- on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt
05000206/LER-1997-001-01, :on 970107,security Test/Insp Was Missed.Caused by Individual Responsible for Security Sys Tests/Insp Failing to Ensure Tests Completed.Implemented Required Compensatory Actions1997-03-0606 March 1997
- on 970107,security Test/Insp Was Missed.Caused by Individual Responsible for Security Sys Tests/Insp Failing to Ensure Tests Completed.Implemented Required Compensatory Actions
1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 05000361/LER-1999-005-01, :on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 9908311999-09-23023 September 1999
- on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 990831
ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with 05000206/LER-1999-001-02, :on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension1999-08-31031 August 1999
- on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension
ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 05000361/LER-1999-004-01, :on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired1999-08-0606 August 1999
- on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired
ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services 05000362/LER-1999-005, :on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With1999-07-28028 July 1999
- on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With
05000362/LER-1999-006, :on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With1999-07-26026 July 1999
- on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With
ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with 05000362/LER-1999-003-01, :on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced1999-06-11011 June 1999
- on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced
05000362/LER-1999-004, :on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced1999-06-11011 June 1999
- on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced
ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 05000362/LER-1999-002-01, :on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With1999-05-20020 May 1999
- on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With
ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 05000362/LER-1999-001-01, :on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With1999-03-12012 March 1999
- on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With
05000361/LER-1999-002, :on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With1999-03-10010 March 1999
- on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With
05000361/LER-1999-001, :on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with1999-03-0303 March 1999
- on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with
ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 1999-09-09
[Table view] |
text
_ _ _ _ _ _ _ _ _ _ _ _ _ -.
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e cu Southam Califomia Edison Company SAN ONOF HC NUCLE AM OCNt RATING STAYlON P. O. BOX t es LAN CLEMENT E. CALWORNIA92074-0128 N. W. KfVL GE Ft TEttesowy February 16, 1993 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Docket !Jo. 50-362 30-Day Poport Licensee Event Report No.93-001 San Onofre Nuclear Generating Station, Unit 3 Pursuant to 10 CFR 50.73 (d), this submittal provides the t' squired 30 day written Licensee Event Report (LER) for an occurrence involving an automatic reactor trip. Neither the health nor the safety of plant personnel or the public was affected by this occurrence.
If you require any additional information, please no advise Sincerely,
~
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Enclosure:
LER Ho.93-001 cc:
C.
W.
Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3)
J.
B.
Kartin (Regional Administrator, USNRC Region V)
Institute of Nuclear Power Operations (INPO) 22009 4 fp maamat2%2 r
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e i
LICENSEE EVENT RtTORT (LER) f5Tility Name (1) lDocketkwber(2)
_Page v3) _
SAN ONOFRE NUCLEAR GINfDATING STAftDN UNIT 3
! 0! $! O! 01 O! 3! 6! 2 1 of 0 4 iltle (4)
AUTOMATIC TURBlNE/ REACTOR TRIP DUE TO MAIN GENERATOR STATOR GROUND PROTECTION ACTUATION CAUSED BY WATER INTRUSION EVENT DAff M T LER NUMi>ER (6)
REFoki DATE (7) 01TTR71TiflilES INVOLVED (8)
Month ay Year Veer l///5equen'ial
/// Revision Month Day jYear f acility Neilis 7ocket Ntr6er(s) 7
///
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///
Ntrbe r NONE 015101 O! O! ! !
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POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v)
Other (Specify in 73.71(c)
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20.405(a)(1)(iii) 50.73(a)(2)(1) 50.73(a)(2)(vtf)
- - Abst ract below and 20.405(a)(1)(ti) 50.36(c)(2) 110)
! 7 !5 50.73(a)(2)(vili)(A)
' T/7////////////////////T/
Z 20.405(a)(1)(iv) Z 50.73(a)(2)(ii)
- 50. 73(a)( 2 )(m ii )(8) in text)
/////////////////////////
20.405(a)(1)(v) 50.73(a)(2)(iii) __ 50.73(a)(2)(i)
/////////////////////////
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LICENSEE CONTACT FOR THl$ Ele (12)
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' Name i
Tj,LEPHONE NU%ER I AREA CODE '
Station Mananer 711!4 !3!6!81-!6!2!5!5 COMPLETEONELih6FOREhCHCOMPONENTFAILUREDESCRIBEDINTWik(REFok R. W. K riepr.
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TURER TO NPFDS
//////
9 I ///////
//////
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!///////
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I'_PPMlMALREPORF g
U EXPECTED (14)
Month,Dayj Year g
Expected
~
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'I
'!X!'NO Date (15)
Ye g lKitTsic. (Lys. cospete 9PL:TED SUBMISSION DATE) timit to 141i0 spaces, i.e.,
upproximately fifteen single-space types-itten lines) (16)
On January l' 1993, Unit 3 was operating at 75% power with a 'neavy rain storm occurring.
at 1641, the hiain Generator tripped on a stator ground protection signal, causi' turbine / reactor trip.
The plant was stabilized in Mode 3 at normal tempel. are and pressure at approximately 1715, Rain water leaked down from the turbine deck into the main generator terminal enclosure, which containu the transition from the main generator conductors'to the isophase bus.
The water accumulated on some insulating material and provided a low resistance path from the exposed B phase conductor ta ground, actuating a Main Generator / Main Turbine trip signal.
Additional sealing wes provided for the Main Generator terminal enclosure to minimize the possibility of rain water intrusion, and the insulating material was replaced.
SCE will evaluate whether additional measures can be taken to minimize the possibility of l
rain water intrusion into the Main Generator components.
The e in no safety significance to this event since all Reactor Protection System compenents operated ao designed.
l t
I
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.O LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 3 05000362 93-001-00 2 of 4 Plant: San Onofre Nuclear Generating Station Unit: Three Reactor Vendor: Combustion Engineering Event Date: 01-16-93 Time: 1641 A.
CONDITIONS AT TIME OF THE EVEITT:
Mode:
1, Power Operation (75% Power)
B.
BACKGROUND INFORMATION
1.
Main Generator:
The Main Generator (TB, GEN] at San Onofre is located on the turbine deck which is not an enclosed structure.
The Main Generator is protected by-relaying devices
[. LY] designed to detect abnormal conditions, including R
stator grounds.
The stator ground trip circuit protects the generator against a ground en the stator or on equipment connected to any of the stator phases (e.g.,
generator terminals, which are located in a terminal enclosure below the Main Generator),
Upon sensing a ground, a stator ground protection signal is initiated to trip the Main Generator and the Main Turbine [TRB).
The Main Generator terminal enclosure is fabricated from aluminum and f.iber board and is bolted between the underside of the Main Generator and the top of the Isophase Bus (EA, IPBU),
The enclosure contains six terminal bushings (one for each phase and three connected to the neutral ground).
The bushings connect each phase of the Main Generator stator windings to the respective output conductors of the Isophase Bus.
The Isophase Bus conducts the power produced by the Main Generator to the main and unit auxiliary transformers. [XFMR]
The transition from the Main Generator output conductors to the isophase bus _is contained-within the Main Generator terminal enclosure.
2.
Reactor Protection System (RPS) (JC]-
When above 55% reactor power, a Main Turbine trip causes the RPS to initiste a Loss of Load signal to trip the reactor [AC).
3.
Main Feedwater Pump (MFWP) (SJ, P] Speed Control (JK]
Following a reactor trip, MFWP speed automatically slows to a minimum speed setting. This setting is intended to maintain MFWP discharge pressure higher than expected steam generator (SG) [SG.1 pressure, thereby maintaining flow to the SG's.
o LICENSEE EVENT REPORT (LER) TEXT CON'I'INUATION SAN ONOFRE UUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE p))IT 3 Q1222]E2 9}-001-00 3 of 4 C.
DESCRIPTION OF THE EVENT:
1.
Event:
On January 16, 1993, Unit 3 wan operating at 75% power with a heavy rain storm occurring. At 1643, the Main Gonai ntor tripped on a stator ground protection signal, causing a turbine / reactor trip.
The plant was stabilized in Mode 3 at normal temperature and pressure at approximately 1715.
2.
Inoperable Structures, Systemn o:' Components that Contributed to the Event:
None 3.
Sequence of Evento:
TIME S Q QN 1641 Main Generator atator ground protection nignal caused a turbine / reactor trip.
1715 Plant conditionn were atabilized in Mode 3, 4.
Method of Discovery
Control room alarma and indications alerted the control room operators to the turbine / reactor trip.
5.
Personnel Actions and Analyais of Actionn:
Control room operatorn renponded properly to the reactor trip, implementing normal post-trip procedures to stabilize the plant in Modo 3.
6.
Safety System Responnen:
The RPS componento actuated as required by design.
D.
CAUSE OF THE EVENT
1.
Immediate Caune:
A Main Generator stator ground protection signal caused a Main Generator / Main Turbine trip.
The turbine t: 1p caused a reactor trip on a loca of load signal.
2.
Root Cause:
An inspection of the Unit 3 main generator terminal enclonure was performed.
Thin enclosura contains the tranaition from the main generator. conductor to the.iuophase bus.
Rain water (the site received an unusually high amount r rainfall combined with high winda prior to the_ trip) leaked down from the turbine deck through openingo into this enclocure. The water accumulated on
\\ $*.
+
4 LICENSEE EVENT-REPORT (1.ER)- TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 3 05030362 931001-00' 4 of 4 some insulating material and provided a low resistance' path;from the exposed B phase conductor to ground. This resulted in phase B;to ground current being detected by the stator ground relay, actuating a Main Generator / Main Turbine trip signal.
E.
CORRECTIVE ACTIONS
1.
Corrective Actions Taken:
Since the turbine building is open to the elements and due to'the configuration of the main generator to isophase bus housing, it is not feasible to provide absolute protection against wind driven water intrusion.
However, additional sealing was provided for the Main Generator terminal enclosure to minimize the possibility of rain wat3r intrusion, and the insulating material was replaced. During the subsequent plant recovery, the Main Generator was monitored to ensure acceptable performance.
2.
Planned Corrective Actions
SCE will evaluate whether additional measures can be taken to minimize the possibility of rain water intrusion into Main Generator components.
F.
SAFETY SIGNIFICANCE OF THE EVENT:
There is no safety significance to this event since all RPS components operated as designed.
G.
ADDITIONAL INFORMATION
1.
Component Failure Information
Not applicable 2.
Previous LERs for Similar Events:
None 3.
MFWP Response:
During the post trip response, MFWP minimum speed setting.was such that MFWP=
discharge pressure was below SG pressure, causing SG levels to decrease.
Control room operators (utility, licensed) properly took manual control of MFWP speed to maintain SG levels. The Main Feed Water Pump minimum speed settings were adjusted. During the subsequent plaat recovery, the Main Feed Water Pump speed was monitored to ensure acceptable cerformance. SCE will evaluate whether additional measures should be taken to minimize the possibility of low MFWP specd during post trip conditions.
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05000362/LER-1993-001, :on 930116,main Generator Tripped on Stator Ground Protection Signal Causing Turbine/Reactor Trip.Caused by Water Intrusion.Addl Sealing Provided for Main Generator Terminal Encl to Minimize Water Intrusion |
- on 930116,main Generator Tripped on Stator Ground Protection Signal Causing Turbine/Reactor Trip.Caused by Water Intrusion.Addl Sealing Provided for Main Generator Terminal Encl to Minimize Water Intrusion
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | 05000361/LER-1993-001-01, :on 930208,engineer Notified That MSSV Inoperable Due to Removal of Insulation from Valve Body. Caused by 930204 Removal of Insulation to Investigate Leak in Discharge Flange.Warning Signs Added |
- on 930208,engineer Notified That MSSV Inoperable Due to Removal of Insulation from Valve Body. Caused by 930204 Removal of Insulation to Investigate Leak in Discharge Flange.Warning Signs Added
| 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 50.73(a)(2)(iii) 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) | 05000361/LER-1993-002, :on 930225,125 Vdc Battery Charger 2B001 & 2B002 Declared Inoperable.Caused by Incorrect 10CFR21 Evaluation.Original 10CFR21 Evaluation for 125 Vdc Charger Reactor Circuit Boards Will Be Revised |
- on 930225,125 Vdc Battery Charger 2B001 & 2B002 Declared Inoperable.Caused by Incorrect 10CFR21 Evaluation.Original 10CFR21 Evaluation for 125 Vdc Charger Reactor Circuit Boards Will Be Revised
| 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 50.73(a)(2)(iii) 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) 10 CFR 50.73(s)(2)(vii) | 05000362/LER-1993-002-01, :on 930309,discovered That TS Surveillance Required to Be Performed at Least Once Per 24 H Had Not Been Performed.Caused by CR Operator.Refresher Training Will Be Conducted for All License Operators |
- on 930309,discovered That TS Surveillance Required to Be Performed at Least Once Per 24 H Had Not Been Performed.Caused by CR Operator.Refresher Training Will Be Conducted for All License Operators
| 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 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) | 05000362/LER-1993-003, :on 930527,discovered Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves Secured |
- on 930527,discovered Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves Secured
| 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 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) | 05000361/LER-1993-003-01, :on 930730,discovered Plant Low Pressurizer Pressure Trip Setpoint Not in Conformance W/Ts Requirements. Util Reset Setpoint to Be in Compliance W/Tss & Submitted Proposed TS Changes |
- on 930730,discovered Plant Low Pressurizer Pressure Trip Setpoint Not in Conformance W/Ts Requirements. Util Reset Setpoint to Be in Compliance W/Tss & Submitted Proposed TS Changes
| 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)(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) | 05000362/LER-1993-004, :on 930705,reactor Tripped Due to Loss of Vacuum.Replaced Failed Instrument Air Tubing & Inspected Tubing for Units 2 & 3 |
- on 930705,reactor Tripped Due to Loss of Vacuum.Replaced Failed Instrument Air Tubing & Inspected Tubing for Units 2 & 3
| 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)(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) | 05000361/LER-1993-004-01, :on 930802,portions of Shift Surveillance Not Performed.Caused by Personnel Error.Plant Operators Counseled on Procedures |
- on 930802,portions of Shift Surveillance Not Performed.Caused by Personnel Error.Plant Operators Counseled on Procedures
| 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)(x) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(n)(2)(ii) 10 CFR 50.73(n)(2)(iii) | 05000362/LER-1993-005-01, :on 931130,determined That CCW Return Valve 3HV6371 Incorrectly Assembled.Investigation of Incorrect Assembly of Subj Valve Initiated.Investigation Rept Will Be Complete by 940131 |
- on 931130,determined That CCW Return Valve 3HV6371 Incorrectly Assembled.Investigation of Incorrect Assembly of Subj Valve Initiated.Investigation Rept Will Be Complete by 940131
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(B) | 05000362/LER-1993-005, :on 931130,containment Isolation Valve 3HV6371 Failed to Open.Caused by Inverted Upstream Skirt.Valve Correctly Assembled,Tested & Determined Operable During Refueling Outage |
- on 931130,containment Isolation Valve 3HV6371 Failed to Open.Caused by Inverted Upstream Skirt.Valve Correctly Assembled,Tested & Determined Operable During Refueling Outage
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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(e)(2)(iv) | 05000361/LER-1993-005, :on 930810,identified Improper Configuration of Units 2 & 3 MSIV Enclosure Blowout Panels Due to Inadequate MP for Installation.Restored Blowout Panels to Operability on 920930 |
- on 930810,identified Improper Configuration of Units 2 & 3 MSIV Enclosure Blowout Panels Due to Inadequate MP for Installation.Restored Blowout Panels to Operability on 920930
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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) | 05000362/LER-1993-006, Forwards RCE-94-002, Reactor Coolant Pump 3P002 Mechanical Seal Failure, as Committed in LER 93-006,dtd 940112 | Forwards RCE-94-002, Reactor Coolant Pump 3P002 Mechanical Seal Failure, as Committed in LER 93-006,dtd 940112 | | 05000362/LER-1993-006-01, :on 931213,reactor Protection Sys Actuation Occurred During Mode 3.Caused by Manual Trip of RCP 3P002. No Corrective Actions Necessary |
- on 931213,reactor Protection Sys Actuation Occurred During Mode 3.Caused by Manual Trip of RCP 3P002. No Corrective Actions Necessary
| 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)(x) 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) | 05000361/LER-1993-006, :on 930908,determined tornado-generated Missile Barriers Were Not Fully Met Due to Inappropriate Initial Design Work.Util Will Revise Licensing Basis for tornado- Generated Missile Barrier Protection |
- on 930908,determined tornado-generated Missile Barriers Were Not Fully Met Due to Inappropriate Initial Design Work.Util Will Revise Licensing Basis for tornado- Generated Missile Barrier Protection
| 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)(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)(viii)(B) | 05000362/LER-1993-007-01, :on 931128,EDG 3G002 Output Breaker Tripped. Caused by Two Failed Bolts.Corrective Action:Failed Bolts Were Replaced & Tested |
- on 931128,EDG 3G002 Output Breaker Tripped. Caused by Two Failed Bolts.Corrective Action:Failed Bolts Were Replaced & Tested
| 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)(iii) 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) 10 CFR 50.73(a)(2)(1) | 05000361/LER-1993-007, :on 930921,determined That non-conservative Error Made in Input to Original Large Break LOCA (LBLOCA) Analysis Which Affected Calculated Peak Fuel Cladding Temp. Existing LBLOCA Analysis Reevaluated |
- on 930921,determined That non-conservative Error Made in Input to Original Large Break LOCA (LBLOCA) Analysis Which Affected Calculated Peak Fuel Cladding Temp. Existing LBLOCA Analysis Reevaluated
| 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)(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) | 05000361/LER-1993-008, :on 931022,sample Blower for Hydrogen/Oxygen Monitors for Wg Surge Tank Inadvertently Turned Off W/Wg Holdup Sys Operating Due to Day Shift Radwaste Operator Inadequate Knowledge of Sys.Operator Retrained |
- on 931022,sample Blower for Hydrogen/Oxygen Monitors for Wg Surge Tank Inadvertently Turned Off W/Wg Holdup Sys Operating Due to Day Shift Radwaste Operator Inadequate Knowledge of Sys.Operator Retrained
| | 05000361/LER-1993-009, :on 931025,inadequate Control of Watertight Doors Identified.Watertight Barriers Closed & Temporary Controls & Compensatory Actions Established |
- on 931025,inadequate Control of Watertight Doors Identified.Watertight Barriers Closed & Temporary Controls & Compensatory Actions Established
| 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 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) | 05000361/LER-1993-009-01, :on 931025,inadequate Control of Watertight Doors Occurred.Immediate Steps Taken to Clear & Close Affected Watertight Barriers.Initiated Administrative Controls for Barrier Configurations |
- on 931025,inadequate Control of Watertight Doors Occurred.Immediate Steps Taken to Clear & Close Affected Watertight Barriers.Initiated Administrative Controls for Barrier Configurations
| 10 CFR 50.73(a)(2) | 05000361/LER-1993-010, :on 931122,Train a ECCS Declared Inoperable Due to Configuration of Containment Sump Cover Plate.Debris Limiting Collar Promptly Installed Around LTOP Pipe Penetration of Train a Sump Cover Plate |
- on 931122,Train a ECCS Declared Inoperable Due to Configuration of Containment Sump Cover Plate.Debris Limiting Collar Promptly Installed Around LTOP Pipe Penetration of Train a Sump Cover Plate
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | 05000361/LER-1993-011, :on 931130,discovered Incorrect Low SG Pressure Setpoint Due to Faulty Meter.Restored Low Setpoint to Proper Value,Repaired Meter & Counselled Operators |
- on 931130,discovered Incorrect Low SG Pressure Setpoint Due to Faulty Meter.Restored Low Setpoint to Proper Value,Repaired Meter & Counselled Operators
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
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