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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
~CATEGORY3yREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9904090149 DOC.DATE:
99/04/07NOTARIZED:
NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPowerSLightCo.AUTH.N9ME
.AUTHORAFFILIATION MADDEN,G.R.
FloridaPower6LightCo.STALL,J.A.
FloridaPower&:LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000389
SUBJECT:
LER99-002-00:on 990311,SG ECTerrorcausesoperation withcondition prohibited byTS.Caused bydeficiencies indataanalysis'guideline instructions.
Licenseewillchangedataanalysisguidelines forleadanalysts.
With990407ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD2-3PDINTERNAL:
ACRSAEOD/SPD/RRAB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB EXTERNAL:
LSTLOBBYWARDNOACPOOREiWNRCPDRCOPIESLTTRENCL11111'1111,11111111RECIPIENT IDCODE/NAME GLEAVES,W AEODSPD/RABLECENTNRRDRCHHQMBNRR/DSSA/SPLB RGN2FILE01LMITCOMARSHALLNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL112211111111111111D0NNOTETOALLnRIDS>iRECIPIENTS PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPZESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR19ENCL19 FloridaPower&LightCompany.6351S.OceanOrive,JensenBeach,FL34957~FPtApril7,1999L-99-8610CFR$50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:1999-002-00 DateofEvent:March11,1999SGECTErrorCausesOperation withaCondition Prohibited bTechnical Seciftcations TheattachedLicenseeEventReport1999-002isbeingsubmitted pursuanttotherequirements of10CFR$50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallSiteVicePresident St.LucieNuclearPlantJAS/EJW/GRM Attachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LucieNuclearPlant9904090149 990407PDRADQCK05000389SPDRanFPLGroupcompany NRCFORM366(6-1996)U.S.NUCLEARREGULATORY COMMISSION jLICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNO.3150.0104 EXPIRES06/30/2001 Estimated burdenperresponsetocomplywithlhismandatory information collection request:50hrs.Reportedlessonsloomedareincorporated Intolhelicensing processandfedbacktoIndustry.
Fonrrardcommentsregarding burdenestimateloIheRecordsManagement Bmnch(TAF33),U.S.NuckrarRegulatory Commission, Washington,
)3C205554001
~andtothePaperwrxk Reduction Proioct(31500104j, OfficeofManagement andBudget,Washington, Dc20503.Ifanfnfonnalion collection doesnotdispbryacurrently validOMBcontrolnumber,theNRCmaynolconductorsponsor,andapersonisnotrequiredtorespondlo,IheInformation collection.
FACILITYNAME(1ISt.LucieUnit2DOCKETNUMBER(2)05000389PAGE(3)Page1of6TITLE(4)SGECTErrorCausesOperation withaCondition Prohibited byTechnical Specifications EVENTDATE(5MONTHOAYYEARLERNUMBER6lSEQUENTIAL REVISIONNUMBERNUMBERREPORTDATE(7)MONTHDAYFACILITYNAMEYEAROTHERFACILITIES INVOLVED(BlOOCKETNUMBER031119991999-002-00,0407FACILITYNAME1999OOCKE'rNUMBEROPERATING MDDE(9)POWERLEVEL(10)100THISREPORTISSUBMITTEDPURSUANTTOTHEREQ20.2203(a)(2l(v) 20.2203(a)
(3)(i)20.2201(b) 20.2203(sl(1)X50.73(a)(2)(i) 50.73(a)(2)(u) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(3)(u) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(BH2)(iv)
UIREMENTS OF10CFR%t(Checkoneormore)(11)50.73(s)(2)(vin) 50.73(a)(2)(x)73.71OTHER20.2203(sl(2)(iii)20.2203(a)(2)(iv) 50.36(c)(1) 50.36(c)(2)50.73(a)(2)(v) 50.73(a)(2)(vii)
SpecifyinAbstractbeloworInNACForm366ANAMELICENSEECONTACTFORTHISLER(12)TELEPHONE NUMBERSneIIereArseCedetGeorgeR.Madden(561}467-7155COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13)CAUSESYSTEMCOMPONENT MANVFACTVAEA REPORTABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(14IYES(I(Yes,completeEXPECTEDSUBMISSION DATE).evIntaXNoEXPECTEDSUBMISSION DATE(15)MONTHDAYABSTRACT/limitto1400spaces,/.e.,approximately 15single.spaced typewritten lines/(16)DuringtheSt.LucieUnit2refueling outage11(SL2-11}steamgenerator inspection inNovember1998,thetubeatRow49Line85insteamgenerator (SG}2Bwaspluggedduetoawear-induced indication thatpenetrated 47%throughwall,exceeding theplugginglimitofTechnical Specification 4.4.5.4.a.6.
Uponreviewofhistorical data,itwasdetermined thatthisindication waspresent,butnotidentified duringtheSL2-9andSL2-10examinations, andthatthedepthofthei.ndication wasessentially unchanged duringthisperiodofoperation.
Therefore, thistubeexceededtheplugginglimit,butremainedinserviceduringoperating cycles9and10.Detection andsubsequent pluggingofthistubeindication resultedfromimprovements inthedataanalysisandcontrolsimplemented fortheSL2-11inspection.
LeadanalystsdidnotinformFPLthatthisindication wasnotidentified duringthepriorexaminations.
Themisseddetection wasidentified duringthepostoutagereviewacti.vities.
Corrective actionsinclude:changingdataanalysisguidelines forleadanalyststoreportconditions toFPLthatmayindicatearepairable degradation wasnotreportedinapriorexamination; modifying dataanalysisguidelines forwear-induced degradation toincludeinstructions toscreenthe100kHzdifferential and100kHzabsolutechannelsinadditiontothe400/100kHzdifferenti.al mixchannel,andreportflaw-like indications; andincluding thewearindications thatwereidentified duringtheSL2-11inspections, butnotreportedinSL2-10inspections, inthetrainingandtestingofdataanalysispersonnel.
NACFORM366I6.1996)
NRCFORM366A(8-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAMEI1)St.LucieUnit2~DOCKETNUMBERI2)05000389LERNUMBERI6)SEQUENTIAL REVISIONNUMBERNUMBER1999-002-00PAGEI3)Page2of6TEXT(Ifmorespeceisrequired, useadditionel copiesofNRCFarm366A)I17)EventDescription OnMarch11,1999,apostoutagereviewofthesteamgenerator (SG)[EIIS:AB:SG) tubedegradation trendswasbeingpreparedforthefall1998refueling outage(SL2-11)steamgenerator examination report.Itwasnotedthatawear-induced indication inthetubeatRow49Line85ofSG2Bwasreportedas47%throughwallanddidnotshowanyevidenceofgrowthbasedoncomparison totheSL2-10examination data.ThistubewaspluggedduringtheSL2-lloutage.Thisreviewconfirmed thatthisindication waspresentintheSL2-10examination data,andmeasuredapproximately thesamedepth,butwasnotreported.
Althoughtheleadreviewteam(LRT)analysts(contractors) hadmadethissamedetermination duringtheSL2-11examination, itwasnotbroughttotheattention oftheFPLrepresentative.
Amoreextensive reviewonMarch12,1999determined thattheindication wasalsopresentintheSL2-7,SL2-8andSL2-9examination dataandwasnotreportedbyeithertheprimaryorsecondary analysts(contractor).
Thisreviewshowedthattheindication didnotexceedtheplugginglimit(40%.throughwall)ofplantTechnical Specifications untiltheSL2-9andlaterexaminations.
IntheSL2-11examination, theindication wasnotreportedbytheprimaryanalyst(contractor),
butwasidentified bythesecondary analyst(contractor) throughtheuseofacomputerdatascreening system(CDS).TheCDSsystemusespre-established screening parameters thatarequalified todetectdegradation thatisknownorpostulated toexistintheSGs.DuringtheSL2-11examination, theCDSsystemparameters wereenhanced"to screenforpotential free-spancracking, whichhasbeenreportedduringprevious'examinations intheSt.LucieUnit1(original SGs),SONGS,andCalvertCliffsSGs.Theenhancedscreening parameters usedforfree-span crackingoverlapped thesameregionofthetubebundleinwhichthediagonalsupportwear-induced indications occur,andresultedindetection ofthewear-induced indication thatpreviously wasnotreported.
CauseoftheEventAbarrieranalysiswascompleted todetermine thecausesthatcontributed tothisevent.Thecausesfornotreporting theindication intheSL2-10examination weredetermined tobe;1)deficiencies indataanalysisguideline instructions, and2)inadequate dataanalysttraining.
Inaddition, thedataanalysisguideline didnotinstructleadanalysts(contractor) toreportconditions toFPLthatmayindicatethatarepairable degradation wasnotreportedinpriorexaminations.
Thiswouldprovideearlieridentification ofpotential problems.
Areviewofindustryqualified examination techniques providedthroughEPRIshowsthat,forwear-induced indications, screening ofthe400/100Khz differential mixchannelisoneofseveralacceptable techniques.
Latitudeisgivenfortheusertospecifyadditional channelstobescreenedforconfirmation andtoprovideadditional instructions.
Thisinformation hasbeensharedwithEPRIfortheirreview.Withtheexception oftheaddedinstructions toscreenthe100Khzdifferential channelforfree-span crackinginSL2-11,thedataanalysisguideline intheSL2-10andSL2-llexaminations wereidentical withrespecttothescreening andreporting ofwear-induced indications.
Theguideline requiresthattheindication appearflaw-likeonthe400/100kHzdifferential mixchannel,oronthe100kHzabsolutechannel.AreviewofSL2-11datashowsthisindication maintains flaw-like characteristics considered typicalofwear-induced degradation onthe100Khzdifferential and100Khzabsolutechannels, butdoesnotmaintaintheminthe400/100Khz differential mixNRCFORM388AI8.1998)
NRCFORM366A(6-I998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAMEI1)St.LucieUpit2OOCKETNUMBERI2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUM8ERNUMBER1999-002-00PAGEI3)Page3of6TEXTfifmorespaceisrequired, useedditionel copiesofNRCForm366A)I17)channel.Theapparentlackofflaw-like characteristics inthe400/100Khz differential mixchannelmaybeattributable toalongerandmoregradualtaperassociated withsomediagonalsupportwear-induced indications.
Thiswouldexplainthelackofflaw-like characteristics inthe400/100Khz differential mixchannel,andprovideanexplanation whytheindication wasnotreportedduringpreviousexaminations.
Theguideline doesprovidelatitudetoreportindications notspecifically addressed ordescribed withintheguideline (Section15.8),yettheindication remainedunreported.
Xnretrospect, theguideline shouldrequiredataanalysispersonnel toreportsuspected wear-induced indications ifanyoftheabovechannelsappearflaw-like.
Thislogicshouldbeappliedtobothprimaryandsecondary analysisreviews.Theindividual analysts(contractor) thatreviewedthedataforthisindication hadpreviousSt.LucieUnit2experience aswellassimilarplantexperience, andarefromreputable organizations.
Furthermore, theirperformance demonstration testresultsdonotindicateaproblemwithdetection orreporting ofwear-induced indications.
Also,dataanalysts(contractor) aretypically limitedto8-10hourshiftstoreducefatigue.Nospecificexamination date,vendororganization, orworkshiftcanbeidentified asasignificant contributor tothisevent.Thissupportstheconclusion thatpotential inadequacies existintheinstructions providedinthedataanalysisguideline, andthesitespecifictrainingandtestingofdataanalysispersonnel forreporting ofwear-induced indications, ratherthaninpersonnel orequipment relatedissues.Thecurrentguideline doesnotspecifically prompttheleadreviewanalyststoreportconditions toFPLthatmayindicatethatarepairable degradation wasnotpreviously reportedinapriorexamination.
Althoughthiswouldnothaveeliminated thefactthattheindication wasnotreported, itdiddelaytheevaluation ofpotential problems.
Thisagainappearstobeanoversight inthedataanalysisguideline instructions.
AnalysisofSGexamination dataisperformed inaccordance withwritteninstructions andprotocolthatareprovidedinFPLdataanalysisguidelines.
Priortoeachexamination, dataanalysispersonnel (contractor) areindoctrinated, trained,andtestedtodemonstrate proficiency inapplication ofguideline instructions.
Dataanalysispersonnel arealsorequiredtopassanHPRIstandardized trainingandtestingprogramforQualified DataAnalyst.ThedataanalysisprocessatFPLincorporates independent primaryandsecondary analysesforalldataacquired.
Secondary analysis.utilizes computerdatascreening (CDS)methodstoprovideaddedassurance thatallindications arereported.
Ateamofresolution analysts(contractor) dispositions differences betweenprimaryandsecondary analyses.
Leadreviewteams(LRT)(contractor) reviewtheresolution teamoutputforconsistency inapplication ofguideline instructions, selectindications fordiagnostic examinations, selectin-situtestingcandidates andprovidefinalinputtothetubeplugginglist.Inadditiontoroutineanalysisasdiscussed above,reviewsarecompleted toevaluategrowthtrends,assessdetection performance, providedataanalystfeedback, andensurethatallindications reportedinapriorexamination areaddressed inthecurrentexamination.
Theleadreviewanalysts(contractor) areinstructed tousehistorical datatoevaluatecurrentoutageresults.Thisistypically accomplished usingthedatasegmentrecall(DSR)functionprovidedintheanalysissoftware, orbyuseofrawdataavailable onopticaldisksorharddrives.DSRisthefirstcourseofNRCFORM3BBAIB.1998)
NRCFORM366A(81998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBERI2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-002-00PAGEI3)Page4of6TEXT(Ifmorespeceisrequired, useedditional copiesofNRCForm366AJ(17)actionsinceallindications reportedinthepriorexamination shouldbeavailable inthisformat.Thealternative istherawdataondisk.TheabsenceofaflawhistoryonDSRforanindication couldbeusedtoinitiatefurtherevaluations todetermine iftheindication waspresent,butnotreportedinthepreviousexamination, andifitappearedtoexceedthetube-plugging limit.Thisinturnshouldalertleadpersonnel (contractor) toinformtheFPLrepresentative.
Currentscreening instructions inthedataanalysisguideline haveidentified morethan500tubesthatareaffectedbywear-induced degradation, whichistypicalforthesteamgenerator designinstalled atSt.LucieUnit2.Currentinstructions, however,donotaccountforindications thatlackflaw-like characteristics inthe400/100kHzdifferential mixchannel,butmaintainflaw-like characteristics inthe100kHzdifferential or100kHzabsolutechannels.
Areviewofindications thathaveremainedunreported inpriorexaminations showsthatonlyoneindication (Row49Line85inSG2B)hasexceededthetube-plugging limitofPlantTechnical Specifications duringpreviousoperation.
Theadditional screening requirements implemented forfree-span crackingappeartobeeffective inreporting thisformofwear-induced degradation, andshouldberequiredintheanalysisinstructions.
Znaddition, dataanalysisguidelines shouldbemodifiedtoinstructleadanalystpersonnel toreportconditions toFPLthatmayindicatethatrepairable degradation isnotbeingreportedinpriorexaminations.
Dataanalysttrainingandtestingshouldalsoberevisedtoincludewear-induced indications thathavenotbeenreportedinpriorexaminations.
AnalysisoftheEventThiseventisreportable under10CFR50.73(a)(2)(i)(B)asanyoperation orcondition prohibited bytheTechnical Specifications (TS).TS3.4.5statesthateachsteamgenerator shallbeoperable.
Theapplicable ACTIONstatement statesthatwithoneormoresteamgenerators inoperable restoretheinoperable steamgenerator tooperablestatuspriortoincreasing T,above200'F.TSSurveillance 4.4.5.0statesthateachsteamgenerator shallbedemonstrated operablebyperformance oftherequired'ugmented inservice inspection program.TS4.4.5.4.a.6PluggingLimitmeanstheimperfection depthatorbeyondwhichthetubeshallberemovedfromserviceandisequalto40%ofthenominaltubewallthickness.
TS4.4.5.4.a.7 statesthatatubeisunserviceable ifitleaksorcontainsadefectlargeenoughtoaffectitsstructural integrity intheeventofanoperating-basis-earthquake (OBE),aloss-of-coolant-accident (LOCA),orasteamli.neorfeedwater linebreak.Contrarytotheabove,onMarch12,1999,FPLidentified thatSG2Boperatedthroughout operating cycle9and10withthetubeatRow45Line85havinga47%throughwallwearindication.
SafetySignificance Thesteamgenerator tubesaredescribed inUFSARsection5.4.2.1.3.
Thetubesaredesignedtoallowforwallthinningandthegenerators aredesignedtominimizethepotential fordenting.TheUFSARdiscusses considerations forlocalized corrosion leadingtotubedegradation, whichisthepredominant degradation mechanism seenintheindustry.
St.LucieUnit2DesignBasisDocument, Volume9,discusses reactorcoolantsystemintegrity.
Etalsodiscusses thestructural integrity requirements forsteamgenerator tubes,andprovidesanassessment ofmaximumallowable tubewallNAGFOAM366A181998)
NRCFORM366A(8.1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-002-00PAGE(31Page5of6TEXTfifmorospaceisrequired, usoadditional copiesofNRCForm368A)(171degradation thatcansustaintheloadingimposedbynormaloperation andpostulated accidentconditions.
Thisshowsthatamaximumallowable tubewalldegradation of63%iswithinthedesignbasisforthesteamgenerator tubing.Mechanical wearintheUnit2steamgenerators isaresultofadesignflawinthefabrication oftheunits.Thedesignflawwasdiscovered following aprimarytosecondary leakatanotherplantandatSt.LucieUnit2duringCycle2shortlythereafter.
InthetubeleakeventatSt.Lucie2,theleakagewaslimitedtoapproximately 20gallonsperday(gpd).Airejectormonitorsreadilydetectedit,andtheunitwasshutdownwithinafewdays.Thehistorical tubeleaksatSONGSUnit2andSt.LucieUnit2occurredinaregionofthetubebundlethatwasanalyzedtobesusceptible torapidgrowthrates.Preventative tubepluggingwascompleted atSt.LucieUnit2toremovethesusceptible tubesfromservice~Therefore, itiscurrently unlikelythatweardegradation wouldresultinthroughwallpenetration andprimarytosecondary leakageinoneortwocyclesofoperation.
Extensive inspections havebeencompleted ateachrefueling outagesincethattime,andtherateofwearhasbeenlow.Afterimplementation ofpreventive pluggingmeasures, itwasnotexpectedthattherateofwear-induced damagewouldresultinathroughwallpenetration afteroneortwocyclesofoperation.
Furthermore, thepotential effectsassociated withathroughwallpenetration scenariohavebeenshowntohavenoeffectonsafety.Adesignbasissteamgenerator tuberupture(SGTR)accident, asdescribed inChapter15oftheSt.LucieUFSAR,isdefinedasadouble-ended guillotine breakofatubethatresultsininitialprimarytosecondary leakratesinexcessof300GPM.ABB/CEhasperformed prototypical laboratory testingtoempirically determine theleakratefromtubedefectsthatwereintendedtosimulateweardefects,producebytubesupports.
Thesetestsshowed"thatinallcases,whenwear-initiated degradation islesqthanthestructural limitofthetubing,primarytosecondary leakagewouldnotbeexpectedtooccurundernormaloperation orpostulated accidentconditions.
Eveninthemajorityofcaseswhensuchdegradation exceedsthestructural limit,athroughwallpenetration ofthistypewillresultinaleakratelessthanoneGPM,andwouldnotsuddenlyleakinanuncontrolled manner.Thesetestresultshavebeenfurthersubstantiated bytheslowsteadyleakratesthatoccurredduringearlyoperation fromthroughwallpenetrations intheSONGSUnit2andSt.LucieUnit2steamgenerators.
Therefore,'he leakratesthatcouldresultfromweardefectswouldbewithinthecurrentTechnical Specification limitsoftheunitandwould,therefore, represent anoperational concernbutnotasafetyconcern.Asaresult,potential tubedefectsfrommechanical weararenotconsidered asapossibleinitiating eventofaSGTRaccidentbut,rather,asapotential increaseinthenormalsecondary systemradionuclide inventory thatisusedasaninitialcondition forotherChapter15accidentanalyses'econdary systemradionuclide inventories assumedintheUFSARChapter15safetyanalysisarebasedononepercentfailedfuelandacontinuous oneGPMprimarytosecondary leakrate.Asdiscussed above,themostsevereleakratesassociated withtypicalthroughwallwearpenetrations aretypically muchlessthanoneGPM.Inaddition, operation withonepercentfailedfuelisconsidered highlyunlikely.
Hence,actualsecondary systemradionuclide inventories areexpectedtobemuchlessthanthoseassumedintheaccidentanalysis.
Asaresult,theradiological consequences associated withpostulated wear-induced tubeleakagewillbeboundedbythoseaccidents currently described inChapter15oftheUFSAR.NRCFORM309A(9.1998) 0 NRCFORM3BBAIB.I990)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2I05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-002-00PAGE(3)Page6of6TEXTilfmorospecersrequired, useedditionel copiesoflVRCForm3S6A)(17)Itshouldalsobenotedthatoperation withacontinuous oneGPMprimarytosecondary leakrateisanunrealistic assumption.
TheSt.Lucie2Technical Specifications donotpermitoperation'f totalprimarytosecondary leakageexceedsoneGPMthroughallsteamgenerators, orifleakagefromanyonesteamgenerator exceeds720gallonsperday(0.5GPM).StLucieperformsprimarysystemwaterinventory balancesatleastevery72hours,whicharecapableofdetecting leakratesofthismagnitude.
Inaddition, secondary systemradiation monitorsarecapableofdetecting increases insecondary systemradiation thatwouldresult.fromprimarytosecondary leaks.Ineithercase,anorderlyreactorshutdownwouldlikelybeperformed beforesecondary systemradionuclide inventories reachedthelevelsassumedintheaccidentanalysis.
Basedontheabovediscussion, wear-induced degradation inthesteamgenerators isnotasafetyconcern.Inaddition, asdiscussed above,maximumallowable degradation thatwillsustaintheloadingimposedbynormaloperation andpostulated accidentconditions is63%throughwallpenetration.
Sincethedegradation inRow49Line85inSG2Bwas47%throughwall,itdidnotexceedthedesignbasis,andstructural integrity wasnotcompromised.
Therefore, thetubewasnotconsidered unserviceable asdescribed inPlantTechnical Specification Section4.4.5.4.a.7.
Basedontheabovediscussion, theoperation duringcycles9and10withthedegradation inthetubeatRow49Line85at47%throughwalldidnotadversely affectthehealthandsafetyofthepublic.Corrective Actions1.Includeinstructions indataanalysisguidelines forleadanalystpersonnel toreportconditions toFPLthatmayindicatethatrepairable degradation hasnotbeenreportedinpriorexaminations.
2.Modifydataanalysisguidelines forwear-induced degradation toincludeinstructions toscreenthe100kHzdifferential and100kHzabsolutechannelsinadditiontothe400/100kHzdifferential mixchannel,andreportflaw-like indications.
3.Includewearindications thatwerereportedinSL2-11inspections, butnotreportedinSL2-10inspections, inthetrainingandtestingofdataanalysispersonnel forfutureoutages.FailedComponents Identified NoneSimilarEventsLER389-1998-008 NRCFORM300A(0.1990)
