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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr ML17229A7381998-05-21021 May 1998 LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr ML17229A7011998-04-27027 April 1998 LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr ML17229A6761998-04-0202 April 1998 LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr ML17229A6731998-03-26026 March 1998 LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr ML17229A6551998-03-0505 March 1998 LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr ML17229A6281998-02-19019 February 1998 LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr ML17229A6211998-02-0909 February 1998 LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr ML17229A6191998-02-0404 February 1998 LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr ML17229A6161998-02-0303 February 1998 LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr ML17229A6051998-01-27027 January 1998 LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr ML17229A5501997-12-0505 December 1997 LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr ML17309A9091997-12-0202 December 1997 LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr ML17229A5391997-11-26026 November 1997 LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr ML17229A5151997-11-0707 November 1997 LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr ML17229A4991997-10-17017 October 1997 LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr ML17309A9011997-08-27027 August 1997 LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr ML17229A4311997-07-29029 July 1997 LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr ML17229A4241997-07-25025 July 1997 LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr ML17229A3971997-07-11011 July 1997 LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr ML17229A3871997-06-19019 June 1997 LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr ML17229A3841997-06-17017 June 1997 LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr ML17229A3751997-06-0202 June 1997 LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr ML17229A3611997-05-29029 May 1997 LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr ML17229A3491997-05-21021 May 1997 LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr ML17229A3441997-05-13013 May 1997 LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc ML17229A3141997-04-30030 April 1997 LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr ML17229A2951997-03-31031 March 1997 LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr ML17229A2721997-03-21021 March 1997 LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr 1999-07-06
[Table view] Category:RO)
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr ML17229A7381998-05-21021 May 1998 LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr ML17229A7011998-04-27027 April 1998 LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr ML17229A6761998-04-0202 April 1998 LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr ML17229A6731998-03-26026 March 1998 LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr ML17229A6551998-03-0505 March 1998 LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr ML17229A6281998-02-19019 February 1998 LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr ML17229A6211998-02-0909 February 1998 LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr ML17229A6191998-02-0404 February 1998 LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr ML17229A6161998-02-0303 February 1998 LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr ML17229A6051998-01-27027 January 1998 LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr ML17229A5501997-12-0505 December 1997 LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr ML17309A9091997-12-0202 December 1997 LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr ML17229A5391997-11-26026 November 1997 LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr ML17229A5151997-11-0707 November 1997 LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr ML17229A4991997-10-17017 October 1997 LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr ML17309A9011997-08-27027 August 1997 LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr ML17229A4311997-07-29029 July 1997 LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr ML17229A4241997-07-25025 July 1997 LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr ML17229A3971997-07-11011 July 1997 LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr ML17229A3871997-06-19019 June 1997 LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr ML17229A3841997-06-17017 June 1997 LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr ML17229A3751997-06-0202 June 1997 LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr ML17229A3611997-05-29029 May 1997 LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr ML17229A3491997-05-21021 May 1997 LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr ML17229A3441997-05-13013 May 1997 LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc ML17229A3141997-04-30030 April 1997 LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr ML17229A2951997-03-31031 March 1997 LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr ML17229A2721997-03-21021 March 1997 LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr 1999-07-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229B0461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr ML17229B0051999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17241A3581998-12-0909 December 1998 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209. ML17229A9421998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17241A4931998-11-0101 November 1998 Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project). ML17229A9051998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr ML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8721998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8611998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17229A8481998-08-0707 August 1998 Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr. ML17229A9461998-08-0707 August 1998 Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr. ML17229A8301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr ML17229A7701998-05-31031 May 1998 Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr 1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRXBUTZON SYSTEM (RIDS)
ACCESSION NBR: 8712220118 DOC. DATE: 87/12/16 NOTARIZED: 'NO DOCKET NACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION POWELL,J.M. Florida Power & Light Co.
WOODY,C.O. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 86-011-01:on 860709,both diesel generators out of svc.
W/8 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR i ENCL j SIZE-TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES S
RECIPXENT COPIES RECIPIENT XD CODE/NAME PD2-2 LA TOURIGNY,E LTTR ENCL
'1 1
1 1
ID CODE/NAME PD2-2 PD COPIES LTTR ENCL 1 1 j A
INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DS P/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DES T/ELB 1 1 NRR/DEST/XCSB 1 1 NRR/DEST/MEB 1 1 NRR/DES T/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 I
NRR/~DRI.S/S B 1 1 NRR/PMAS/ZLRB 1 1
~REG~LE~ 02 1 1 RES DEPY GX 1 1 RES TELFORD,J 1 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G GROH,M 5 5 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 j
A TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45
Wr
~ ~
NRC Form $ 55 UA. NUCLEAR REOULATORY COMMISSION (94$ )
APPROVED OMS HO. $ 1500104 LICENSEE EVENT REPORT (LER) EXPIRES: S/$ 1ISS FACILITYNAME ll) DOCKET NVMSER l2) PA 5 TITLE lcl ST. LUCZE UNZT 2 050003891OF06 BOTH DIESEL GENERATORS SZMULTANEOUSLY OUT OP SERVZCE DUE TO ONE PERSONNEL ERROR AND ONE COMPONENT PAZLURE EVENT DATE (5) LEA NVMSEA (5) RCPORT DATE ITI OTHER SACILITICS INVOLVED (Sl MONTH OAY YEAR YEAR I)$ SCOVCNTIAL ~
NVMOCA ÃA NVMOSA II4 VrtlON MONTH OAY YEAR FACILITYNAMES DOCKET NUMSER(SI N A 0 5 0 0 0 0 7 0 9 8 6 0 1 1 0 1 1I2 1687 0 5 0 0 0 THIS RKPORT IS SVSMITTKD PV ASVANT T0 THE REQVIAEMENTS OF 'lo CSA : ICIrccp circ IN moro ot too Iollowprol (11 OPERATINO $
MODE (SI 20A02(b) 20.405(cl SO.T $ 4)(2) litI T$ .710r)
POWER 20.405( ~ )(till) SOW(cl(t) 50,1$ 4)l2)lrl TS.7 I(cl LEYKL HO) 1 0 20A05(c I I I I (5) SOM(cl(2) 50.224)(2)(rIII DTHER Ispoclty In Aorrroct 20.405(c) (I l(ill) EO.T $ (cl(2) (Il 50 2 $ 4) l2) (rhll(AI OHowcnrtln Tert HIIC F~
$ 5EAI 20AO54 ln l(lr) SO.TSlc)l2)(S) 50.2$ (c)(2)(HEI(S) 20.405 (cl II I 4l SO.T $ 4) (2) (IE) 50.2241(2)(cl LICENSEE CONTACT SOR THIS LLh lt2)
NAME TKLEPHONE NUMSCR J. M. Powell, Shift Technical Advisor AREA CODE COMPLETE OHE LINE SOA EACH COMPONENT FAILUAC OCSCh(SCD IH THIS RCPORT l1$ l 3 5465 -35 50 4$ %y4W CAUSE SYSTEM COMPONENT MANUFAC EPORTASLE i r 'spy'; CAUSE SYSTEM COMPONENT MANUSAC. EPORTASL TURER TO NPROS
, 4~iI TURER TO NPRDS EK 65 W29 0 4 @,
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B EK PAN X99 9 4 .?
SUPPLEMENTAL REPORT EXPECTCD I(4) MONTH OAY YEAA EXPECTED SUSMISSION YKS IIIycr, COmolcrc EXI'ECTEO SVSICISSIOHOATEI DATE (15)
NO AssTRAGT ILimit to (coo Ipccrr, I.o., cpprocimcrcly IIItrcn rlnplc.rpocc Iypcwri rtrn IInccl (I ~ I On July 9, 1986, while Unit 2 was at full power, the 2A Emergency Diesel Generator ID/G) was taken out of service due to failure to meet the required start time during a normal surveillance test run. The redundant 2B D/G was subsequently started, came up to rated voltage and frequency within the required time, but was declared out of service as one of the cooling fans was rubbing its shroud.
Repairs were made to both diesels; both were returned to service within the applicable Technical Specification time The failure of the 2A D/G was caused by excessive tightening of a friction clutch locknut. Engineering evaluation of the 2B D/G fan event revealed the presence of resonant frequencies in the 12 cylinder engine, which resulted in the flapping of the fan drive belts. The vibration caused by the flapping belts resulted in the loosening of the fan hub set screws.
Corrective action included:
- 1. Znspection of torque values in all friction clutch locknuts.
- 2. Znstructing all plant D/G maintenance personnel to contact vendors 1
for information regarding component adjustment when necessary.
- 3. A torsionally soft coupling has been instalZed in the fan drive systems on the 12 and 16 cylinder engines.
8712220118 871.216 PDR ADOCK 05000389 8 DCD NRC Form $ 55 (94)$ 1
NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (943(
LICENSEE E NT REPORT (LER) TEXT CONTINUA ON APPROVEO OMB NO. 3I50-0(04 EXPIRESI 8/31/88 FACILITY NAME (1I OOCXET NUMBER (3( LER NUMBER (BI PACE (3) r( SEQVENTIAL ~>& RSVrSION YEAR g$ NVMOOR +4 NVMOSR ST. LUCZE, UNIT 2 TEXT ///more F/>>ce /F n//r/lrerL Iree /I/Oi5onro/NRC Forrrr 388l3/ (In o so oo389 8 6 0 1 1 0 1 0 2 OF 0 6 EVENT DESCRIPTION At 0854 hours0.00988 days <br />0.237 hours <br />0.00141 weeks <br />3.24947e-4 months <br /> on July 9, 1986, St. Lucie Unit 2 was operating at 100%. The Unit rem'ained at 100% throughout the event.
At 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> on July 9, 1986, the 2A Emergency Diesel Generator (D/G) (EZISEEK) was started for a once per*seven (7) days surveillance test (once per 7 days based on" three (3) valid failures within the last 100 valid starts). The 2A D/G failed to meet the required generator voltage and frequency of 4160+420 volts and 60t1.2Hz within 10 seconds after the start signal. An alarm was received which indicated that one of the engines in the 2A D/G set had failed-to start. The engine fail to start alarm is actuated by high differential temperature between the turbo charger exhausts of the engines in the D/G set.
The power unit consists of two (2) EMD diesel engines, a 12 cylinder-645E4 and a 16 cylinder-645E4, driving one (1) Electric Products generator coupled with EMD tandem couplings, forming a diesel-generator assembly. The 2A D/G was manually tripped by the operator at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br />.
At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on July 9, 1986, the redundant 2B D/G was started to satisfy Technical Specification ACTION (a) of Limiting Condition of Operation (LCO) 3.8.1.1, i.e. the performance of Surveillance Requirement 4.8.1.1.2a.4(redundant D/G operability check) within one (1) hour and at least once per eight (8) hours thereafter. This surveillance was performed since the 2A D/G had to be removed from service based on the 08355 failure. The 2B D/G came up to voltage and frequency within ten (10) seconds, therefore, meeting the Surveillance Requirement; 4.8.1.1.2a.4. At 0917 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.489185e-4 months <br /> the 2B D/G was stopped due to an operator observation of one (1) of the 12-cylinder cooling fan blades rubbing the cooling fan shroud.
A decision was made to take the 2B D/G out of service to evaluate the seriousness of the rub. In accordance with ACTION (e) of LCO 3.8.1.1, operability of offsite power sources was verified and immediate actions were taken to repair both the 2A and 2B Diesel Generators.
The 2B D/G rub was determined to be minor and at 1048 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98764e-4 months <br /> repairs were completed on the 12-cylinder engine cooling fan. The 2B D/G was started for an operational check and met the required start time. The 2B D/G was declared back in service at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br />. With the 2B D/G back in service ACTION (a) of LCO 3.8.1.1 was maintained.
Trouble shooting of the 2A D/G revealed a problem in the mechanical portion of the Woodward governor. The problem was corrected and the 2A D/G was returned to service at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on July 9, 1986.
NRC FORM SOOA (943 I
NRC Foim 3ddA U.S. NUCLEAR REOULATORY COMMISSION (943)
LICENSEE E NT REPORT (LER) TEXT CONTINUAT ON APPROVEO OMB NO. 3)EOM)04 EXPIRES: 8/31/88 FACILITY NAME ll) OOCKET NUMBER )1) PAOE l3)
LER NUMBER (8)
V EAII SEOVENTIAL REVISION NVMSER NUM EII ST. LUCZEP UNZT 2 p 6 p p p 3 8 9 8 6 011 0 1 0 3 OF 0 6 TEXT ///more dpece /e redo/ra/, Iree //r/ooe/H/IC %%drm 3BSEB/ )IT)
CAUSE OP EVENT 2B Diesel Generator Set The intermediate cause of the 2B D/G 12-cylinder engine cooling fan event was vibration withj.n the 12-cylinder engine Vertical Cooler Unit (ES-165), thereby, causing the set screws in the fan hub to loosen. With the loosening of the fan hub set screws, the fan shifted and began rubbing the shroud. The root cause of the vibration within the Cooler Unit is a design problem associated with fan drive belt flapping. Engineering evaluation of the problem of belt flapping on the 2B D/G has determined that the root cause of the problem was the presence of resonant frequencies in the 12 cylinder D/G fan drive system which were excited by large inherent 3rd and 6th order forced vibrations of the diesel generator set. The investigation revealed excessively high oscillating torque readings measured on the 12 cylinder power takeoff (PTO), North Pan and South Pan shafts. The peak torque levels were found to exceed the mean torque by factors of 3 1/2 - 5 1/2, and evidence of torque reversals were found.
2A Diesel Generator Set The intermediate cause of the 2A2 diesel failing to start was the failure of a roll pin (Ref. No. 82340-44) in the mechanical section of the Woodward EGB-13P engine governor. This governor consists of an electrical section which operates at or near rated engine speed, and a mechanical section which is mainly used during engine startup and shutdown. During startup, a small speed setting motor is used to run up the mechanical governor to allow the engine to reach rated speed where the electrical governor assumes control of engine speed.
This speed setting motor operates on the linkage of the mechanical governor by a fiiction clutch.
Znvestigations revealed a roll pin which holds the intermediate gear on the pinion shaft of the speed setting controls had broken. This gear arrangement drives the dial stop gear which actuates the upper and lqwer stops of the speed setting motor. With, the failure of the roll pin the speed setting motor runs continuously. Continuous running of the speed setting motor caused excessive wear on the friction clutch which, in turn, allowed excessive slippage of the friction drive shaft and prevented the mechanical governor from demanding sufficient fuel flow to pick up load on the 12-cylinder engine and allowing the electric portion of the goveinqr from taking control at the designated engine speed...
The root cause of the roll pin failure was the result of friction clutch adjustments made on the 2A 12-cylinder D/G mechanical governor as described in LER 389-86-006 (SEE PREVZOUS SZMZLAR EVENTS SECTZON). The root cause of LER 389-86-006 was determined to be a loose locknut in the friction clutch. This allowed excessive slippage and prevented the mechanical governor from demanding sufficient fuel flow to pick up load on the 2A 12-cylinder engine. The corrective action was to tighten the loose locknut on the clutch. The friction clutches are supplied as assembled units and are not required to be disassembled and inspected as part of the vendor's recommended preventative maintenance program.
NRC FORM SddA (943)
NRC Form SQIA UA. NUCLEAR REGULATORY COMMISSION (94LII LICENSEE EYENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3150MIOO EXPIRES: 8/31/88 FACILITY NAME Ill OOCICET NUMBER 13) LER NUMEER IS) PAOE 13)
YEAR SSOVENTIAL IISVISIIIN NVM SII NVMSSII ST. LUCIES UNIT 2 0 6 o 0 0 3 8 6 011 0 1 0 4 OF 0 6 TEXT ///more 4/Mde /3 /Pr/rer/ cd er/I/ir/aire/i/RC %%drrri CSEA'3/ (ITI Previous to tightening the loose locknut a review of the technical manual was completed to determine the torque value for the locknut. A torque value was not supplied in the technical manual. A self-determined adjustment was made and the engine was retested with positive results. Upon later conversations with the vendor it was learned that the locknut and the clutch of the 2A 12-cylinder D/G mechanical governor had been tightened beyond the vendor prescribed torque value. The overtightened locknut provided the stress necessary for the roll pin in the speed setting control to break. Thus, the root cause of this component failure was a cognitive personnel error by utility maintenance personnel.
EVENT ANALYSIS The event is reportable under 10 CFR 50.73(a)(2)(v) as neither diesel generator set was operable between the time the 2B D/G failed and'he 2B D/G was returned to service. This condition is allowed for a period not to exceed two (2) hours by LCO 3.8.1.1, provided both offsite power sources are available. Both offsite power sources were operable throughout this event and the time both D/G sets were out of service was less than two (2) hours (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 44 minutes). Also, as per Surveillance Requirement 4.3.1.1.3, ~Re orts: All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1.
The 2A D/G governor component failure was readily detected during routine surveillance testing. The event was determined to be a valid failure in accordance with Regulatory Guide 1.108.
The 2B D/G 12-cylinder cooling fan event was observed while satisfying ACTION (a) of LCO 3.8.1.1. The effect of the cooling fan rubbing the shroud did not inhibit the 2B D/G set from coming up to voltage and frequency within ten (10) seconds. During troubleshooting it was determined that had for the 2B D/G to perform its safety function the 12-cylinder cooling fan would it been necessary have worn the point of contact on the shroud to where no further rubbing would have occurred. The 2B D/G was taken out of service strictly as a precautionary measure and based on the above observation would not be considered a valid failure per Regulatory Guide 1.108.
it was determined that the event In the unlikely event of a complete loss of AC power (onsite and offsite) for St. Lucie 2 and, for the benefit of a conservative analy39isr the simultaneous loss of offsite power and one diesel generator at St. Lucie 1, the remaining diesel generator in St. Lucie 1 is able to operate the minimum safeguard loads such that both Units are maintained in a safe, hot stand-by condition. The present St. Lucie design does have the capability of electrically connecting the two units (
Reference:
St. Lucie 2 PUSAR, Updated Final Safety Analysis
'eport, Section 8.3.1.1.2,Pg.8.3-19d).
This was the fourth valid failure in the last 100 valid tests. Thus, the current surveillance interval is once per (3) days. This surveillance interval is in conformance with the schedule of regulatory position c.2.d of Regulatory Guide 1.108.
NRC FORM SSSA
'I
NRC FoIm 355A U.S. NUCLEAR REOULATORY COMMISSION (943(
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO. 3150-0(04 EXPIRES: 8/31/88 FACILITY NAME III OOCKET NUMSER (3( LER NUMSER (Sl PACE (31 YEAR N~ SEQVSNTIAI NVMOSII ~
.0+'IEVISION NVM SR ST. LUCZE/ UNIT 2 o s o o o 3 8 9 86 01 0 1 05 OF TEXT /// mac tpeoo II /o9o8a/, ooo sd/O'ono/ HRC /omI JSQS/ (ITI CORRECTIVE ACTONS 2B D G SET The 2B D/G cooling fan shroud was removed and the fan was repositioned in order to provide sufficient clearance between the fan blade tips and the fan shroud.
Upon completion of the re-positioning, the fan hub set screws were securely tightened. Corrective actions resulting from this event are:
A. A list of instructions has been developed describing steps to be taken for preventative maintenance inspections of .the D/G vertical cooling fan units. The purpose of these instructions is to check for loose bolts and to insure fan drive integrity.
B. A torsionally soft coupling has been installed in the fan drive systems on both the 12 and 16 cylinder engines of the Unit 2 D/G sets. The coupling will behave as a dynamic filter to cut off transmission of high order excitation past the PTO sheave. Test runs with a model coupling have shown this to be an effective solution.
2A D G SET The 2A2 D/G governor roll pin was replaced by replacing the dial panel assembly in total; this included both the roll pin and the friction clutch. Adjustments to the stop cams had to be made and a test run was performed with satisfactory results. Corrective actions resulting from this event ares A. An immediate inspection of torque values of the like component, i.e.,
friction clutch locknuts, in the remaining St. Lucie Plant D/G's was made.
B. D/G maintenance personnel have been instructed to make every attempt to contact the appropriate vendor should component adjustments be necessary, particulary in the area where information may nest be provided or discussed in the technical manual.
ADDITIONAL ZNFORMATZON FAILED COMPONENT INFORMATION failure of each D/G set was unrelated. The 2A D/G governor is a Woodward V'he Model EGB-13P. The roll pin (broken component in governor) Reference No. is 82340-44. The 2B D/G cooling fan is part of an ES-165 Vertical Cooler Assembly designed by the OaM Manufacturing Company.
NRC FORM SOOA
o %0 NRC Form 3SSA U.S. NUCLEAR REGULATORY COMMISSION (983)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3IEOM(04 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMSER (3) LER NUMBER (S) PACE (3)
YEAR :gI SEOUENTIAL REVISION NUMSSR ~A
>SINAI NUM ER ST. LUCIE UNIT 2 p 5 p p p 3'89 8 011 0 1 06OF06 TEXT ///more Spree /e oer/ 're/ rree e /capone/HRC %%drIII ESCA'o/ ((7)
PREVIOUS SIMILAR EVENTS LER 389-86-6 reported a previous event where both diesel generators were simultaneously out of service for the following related causes:
On March 10, 1986, the 2B Emergency Diesel Generator (D/G) was taken out of service to repair an idler pulley wheel on the belt-driven engine cooling fan.
On March 12, while performing a required operability surveillance on the redundant 2A D/G, one of the two engines in the diesel generator set failed to start.
Repairs on the 2B D/G were completed and the unit was returned to operable status within the time limit allowed by the applicable Technical Specification.
The damage to the idler pulley is believed to be related to the belt flapping problem which has been observed on the 12 Cylinder engines in the D/G set.
The failure of the 2A D/G was caused by a loose locknut in the friction clutch assembly which operates the mechanical governor used for engine start-up.
Corrective actions were to repair both diesels and inspect the remaining idler pulley wheels on the diesels for similar failures. The friction clutches on the remaining engine governors were inspected during the Unit 2 refueling outage, April 1986.
P. O. BOX 14000, JUNO BEACH, FL 33408 0420 OEGEiViBER 1 6 1987 L-87-513 10 CFR 50.73 U. ST Nuclear Regulatory Commission Attn: Document Control Desk Washington, DE CD 20555 Gentlemen:
Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 86-11 Rev. 1 Date of Event: July 9, 1986 Both Diesel Generators Simultaneously Out of Service Due to One Personnel Error and One Com onent, Failure The attached Licensee Event. Report (LER) is being submitted to update the original LER as indicated.
Very truly yours, c
CD
~ 0 Wo y Execut'ice
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President COW/GRM/gp Attachment cc: Dr. J Nelson Grace, Regional Administrator, II,
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Region USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM/ 0 04 ~ LER 2A FPL Group corrpany