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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
QCATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)1ilACCESSION NBR:9705200337 DOC.DATE:
97/05/13NOTARIZED:
NOFACIL:--.3-335 St.LuciePlant,Unit1,FloridaPo~er&LightCo.AUTH.NAMEAUTHORAFFILIATION BENKEN,E.J.
FloridaPower&LightCo.STALL,J.A.
FloridaPower&Light'o.RECIP.NAME RECIPIENT AFFILIATION EDOCKET05000335
SUBJECT:
IER97-005-00:on 970419,reactor wasshutdownduetoreactorcoolantpressureboundaryleakage.RepairstoRCPBwascompleted
&laSDCtrainwasrestoredtosvc.W/970513 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD2-3PDINTERNAL:
ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTEiNAL:LSTLOBBYWARDNOACPOOREgW~NRCPDRCOPIESLTTRENCL111111111111111111111111RECIPIENT IDCODE/NAME WIENS,L.NRR/DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2FILE01LITCCBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL112211111111111111111111G0D0NNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSIQN REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR25ENCL25
,J FloridaPower8LightCompany,6501SouthOceanDrive,JensenBeach.FL34957May13,1997L-97-13010CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335Reportable Event:97-005DateofEvent:April19,1997ReactorShutdownRequiredbyTechnical Specifications TheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/EJBAttachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlant(I9705200337 9705i3PDRADOCK05000335SPDRpQttUQ(i4anFPLGroupcompanyIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII NRCFORM366(4.95)U.S.NUCLEARREGULATORY COMMISSION LICENBEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDSYOIMNo.31604104EKFNIES04nolssESTIMATED SVROENPERRESPONSEToCOMPLYWITHTHISMANDATOINFORMATION COLLECTION REQUEST:60.0HRS.REPORTEDLESSONLEARNEDAREINCORPORATED INTOTHEUCENSINGPROCESSANOFSACKToeIOUSTRY.
FORWARDCOMMDITSREGARDING SURDENESTIMATTOTHEINFORMATION ANORECORDSMANAGEMENT BRANCHIT.eF33)VN.NUCLEARREGIAATORY COMMISSION.
WASHINGTON, OC206660001 ANDTOTHEPAPERWORK REDUCTION PROJECTI31600104b OFRCE0MANAGEMENT ANDBUDGET,WASHINGTON, OC20603.FACIUTYNAME(1)STLUCIEUNIT1DOCKETNNASBE12l05000335PAGEIsl1OF7TITLE14lReactorShutdownRequiredbyTechnicaI Specifications duetoReactorCoolantPressureBoundaryLeakageMONTHDAY0419SEauENTIAL REVISIONNUM9ERNUMBER97,97-005-00MONTHDAYYEAR051397FACIUTYNAMEFACIUTYNAMEN/AN/ADOCKETNUMSER DOCKETNVMSER OPERAT)NQ MODE(6)POWERLEVELl10)20.2201(b) 20.2203(e) l2)(i)20.2203(0)l2)(iii)20.2203(n)
(2)(iv)20.2203(0)(2)(v)20.2203(o) l3)Iii)50.36(c)ll) 50.36(c)(2) 50.73(0)(2)(i)50.73(n)(2)(iii)50.73(n)(2)(v) 50.73(n)(2)(vii) 50.73(n)(2)(viii) 73.71OTHERSpecifylnAbstractbeloworlriNRCForm3SSANAMEEdwinJ.Benken,Licensing EngineerTELEPHONE NVMSEROnc4deAtesCoal(561)467-7156CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSBPN/AN'.jViE:kj YES(lfyes,completeEXPECTEDSUBMISSION DATE)~XNoEXPECTEDSUBMISSION DATEl15)MONTHDAYYEARABSTRACT(Umitto1400spnces,i.o.,npproximote(y 15single-specod typowritten lines)l16)OnApril18,1997,St,LucieUnit1wasoperating inMode1at100percentreactorpower.Leakagefromaoneinchlineonasafetyinjection (Sl)pipeventwasidentified andsubsequently determined tobereactorcoolantpressureboundary(RCPB)leakage.Theleakagewasrestricted toSafetyInjection
~Tank1B2inventory, andnoreactorcoolantleakageresulted.
Areactor.shutdownwasinitiated onApril19,1997,andwascompleted inaccordance withTechnical Specification requirements.
TheUnitwasplacedinMode5onApril20,1997,toimplement repairs.Duringtheplantcooldown, shutdowncooling(SDC)train1Awasdeclaredinoperable andtheredundant trainwasusedtocompletethecooldown.
TheRCPBleakagewasrepairedandtheUnitwassubsequently returnedtoMode1operation onApril23,1997.TheplantshutdownwasrequiredbyTechnical Specifications duetothe,presenceofpressureboundaryleakage.Thefailuremechanism associated withthepressureboundaryleakagewasdetermined tobehotcrackingofasocketweldassociated withtheSlventline.Thehotcrackingwascausedbyweldcontamination.
Theinoperability ofthe1ASDCtrainwasduetothemisalignment ofaminimumflowrecirculation line,andthepresenceofgasvoidsinthehighpointsofthe1ASDCsuctionline.Corrective ActionsInclude:1)Repairswerecompleted totheRCPBandthe1ASDCtrainwasrestoredtoservice.2)Additional analysiswasperformed toconfirmthefailuremechanism fortheaffectedsocketweld.3)Weldtestingisbeingperformed toevaluateforpotential improvements.
4)The1ASDCtrainwasrestoredtooperation following ventingandinspection.
5)SDCsystemventingprocedures arebeingrevisedtoincludeadditional frequency andtemperature requirements, NRcFORM38$I4.95)
NRCFORM366AI495ILICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-005-002OF7TEXTllfmorespeceisrequired, useedditionelcopiesofOftCForm366AJI17IOnApril17,1997,St.LucieUnit1wasoperating inMode1at100percentreactorpower.At1037,aHighPressureSafetyInjection (HPSI)Pump[EIIS:BQ:P]
wasstartedandinventory wasaddedtotheSafetyInjection Tanks(SIT)inaccordance withnormaloperating procedures.
Following theSITfillevolution, operators notedthatthe1B2SIT[EIIS:BP:TK]
levelwasslowlydecreasing.
Therateofinventory lossintheSITwasobservedtobeapproximately 2.5percentovera6hourperiod.Additionally, operators noticedanincreaseinreactorcavityleakagefromapproximately 0.2gpmto0.45gpm.Basedontheindicated increaseinreactorcavityleakage,areactorcoolantsystem(RCS)[EIIS:AB]
inventory balancewasperformed toevaluateandquantifyRCSleakage.Theinventory balancedetermined thatnochangeinRCSleakageratehadoccurredandvalueswereconsistent withthosedetermined priortofillingtheSITs.Aninvestigation wasinitiated todetermine thesourceoftheindicated increaseinreactorcavityleakage.OnApril18,1997,whileconducting acontainment inspection toidentifythesourceoftheleakage,waterwasobservedintheareaofthe1B2SITpipetrench.Tominimizeradiological
- exposure, aroboticcamerawasdeployedtodetermine thesourceoftheleakage,whichappearedtooriginate from+hevicinityofventvalveV-3"15[EIIS:BP:VTV].
Thisventvalveislocatedwithinthereactorcontainment building(RCB)onthe1B2safetyinjection pipe,upstreamofthe1B2safetyinjection loopcheckvalve(RefertoFigure1).Asampleofleakagewasobtainedandanalyzed, whichindicated aboronconcentration inthesampleof2915partspermillion(ppm).RCSboronconcentration atthetimewasapproximately 840ppm.tAreduction inreactorpowerwasinitiated at2020on'April18,1997,toallowpersonnel toaccessV-3815andcharacterize thesourceoftheleakage.At0150onApril19,1997,withthereactorinMode2atapproximately 10'ercent power,acontainment entrywasmadetoinspectV-3815.Theinspection revealedafailure.ofthesocketweldjoiningtheoneinchventlineforV-3815tothesockoletinthesafetyinjection loopline.Thiswasdetermined tobereactorcoolantpressureboundary(RCPB)leakage,inaccordance with10CFR50.2,andtheactionstatement forTechnical Specification (TS)3.4.6.2wasenteredat0217hours.ActionStatement 3.4.6.2.a, specifies, "WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours."Areactorshutdownwascommenced andSt.LucieUnit1enteredMode3(HotStandby)at0228onApril19,1997.ANotification ofUnusualEventwasmadetotheStateofFloridaat0229'andtotheUSNRCat0245,inaccordance withtherequirements oftheSt.LucieEmergency Planforeventsinvolving RCSpressureboundaryleakage.TheUnitenteredMode4at1405andthe1Bshutdowncooling(SDC)train[EIIS:BP]
wasplacedinserviceat2322hoursonApril19,1997.Operators attempted, butwereunable,toplacethe1ASDCtraininserviceduetoadecreaseinpressurizer
[EIIS:AB:PZR]
levelwhenthesuctionvalvesforthe1ASDCtrainwereopened.The1ASDCtrainwassubsequently declaredinoperable, andtheplantcooldownwascontinued usingthe1BSDCtrain.Unit1enteredMode5onApril20,1997,at0315andtheUnusualEventwasterminated atthattime.Following repaiIaftheaffectedweldonthe182safetyinjection lineandresto.dtion ofthe'ASDCtrain,St.LucieUnit1retuinedtoMode1poweroperation at0153onApril23,1997.
NRCFOIIM366A(4-95)LICENSEEEVENTREPORT(LER).TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEOUENTIAL REVISION3OF797-005-00TEXTIifmorespeceisrequired, useedditionel copiesofIVRCForm366AII17IThereactorshutdownwascompleted inaccordance withTSrequirements forRCSleakageinvolving thereactorcoolantpressureboundary.
'heRCPBleakageoriginated fromasocketweldonaoneinchventlinetoV-3815,locatedonthe1B2safetyinjection header.Whileonly1B2safetyinjection tankvolumewasaffected, andnoreactorcoolantinventory waslostasaresultoftheleak,thesiteoftheleakageisclassified asreactorcoolantpressureboundary, asfurtherdiscussed inthisreport.FailureanalysisoftheaffectedweldontheventlinetoV-3815wasperformed following theevent.Theanalysisconcluded thattheinitiating failuremechanism washotcrackingoftheweldduetocontamination.
Boricacidresidueisconsidered tobethemostlikelycauseofthiscontamination.
The1ASDCtrainwasdeclaredinoperable whenoperations personnel observeddecreases inpressurizer
.levelwhileopeningtheSDCsuctionisolation valves.Localobservations identified thatsystempressureinthe1ASDCtrainwasfluctuating duringattemptstoopenthevalves,andasafetyreliefvalveonthe1ASDCtrain,V-3483,temporarily liftedasdesignedinresponsetothesystempressuretransient.
Subsequent inspection andtroubleshootingofflownoisesinsystempipingbyoperations personnel identified thatamanualrecirculation isolation valve(V-3"<4)forthe1Alowpressuresafetyinjection (LPSI)pumpwasnotfullyshutasrequiredforSDCoperation.
ThisresultedinaflowpathfromtheRCStotherefueling watertank(RWT)whentheSDCsuctionvalvestothepumpwereopened,andwastheprimarycauseoftheindicated decreases inpressurizer levelpreviously discussed.
Uponinspection, thehandwheel forV-3204wasfoundtobedifficult tooperateandappearedtobeclosed,howeveroperators usingavalvewrenchwereabletomanipulate thevalveanadditional twoturnstothefullyclosedposition.
Aworkorderwaswrittentorepairthedefective valveandpreventive maintenance practices arebeingreviewedtoaddressgenericaspects.Systemventingandinspections performed following theeventdetermined thatthepressureresponseobservedinthe1ASDCtrainwascausedbythepresenceofgasvoidsinthehighpointsofthe1ASDCsuctionpipinginconjunction withapartially openLPSIpumprecirculation valve.Thepresenceofvoids,alongwiththepartially openrecirculation valvewouldprovideconditions conducive tosteamflashingandpressurefluctuations intheLPSIpumpsuctionlinewhenreactorcoolantwasinitially alignedtothesystem.VentingoftheSDCpipingisrequiredtobeperformed following systemuseastheresultofasimilareventin1995,howevertheprocedures didnotspecifically requirethatthisbeperformed atambienttemperature.
Thecompletion ofventingfollowing thelastuseoftheSDCsystemmaytherefore nothavebeenadequatetopreventsubsequent degassing (voiding) ofreactorcoolantintheSDCsuctionlines.Consequently, procedural inadequacy wasacontributing factorbynotpreventing conditions whichwerefavorable totheformation ofthe'gasvoidsinthe1ASDCsystem.TS3.4.6.2requiresthatnopressureboundaryleakagebepresentinModes1,2,3and4.TSActionStatement 34.6.2.a,furtherspecifies, "WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing 30hours."St.LucieUnit1vasplacedinMode3,HOTSANDBYe';0228,onApril191997,approximately 23minutesfollowing theidentification ofRCPBleakage.
NRCFORM366AI4.96)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-005-004OF7TEXTlemorespeoeisrequired, useeddidonel copiesofNRCFarm386AJI17)Theplant'entered Mode5at0315onApril20,1997,approximately 25hoursafterentryintoMode3.Basedontheabove,thiseventisreportable under10CFR50.73(a)(2)(i)(A),asacompletion ofaplantshutdownrequiredbytheTechnical Specifications.
According tothedefinition providedintheSt.LucieUnit1TS,PRESSUREBOUNDARYLEAKAGEisdefinedas"...leakage (exceptsteamgenerator tubeleakage)throughanon-isolable faultinaReactorCoolantSystemcomponent body,pipewallorvessel.wall."Additionally, 10CFR50.2definesthe"reactorcoolantpressureboundary" asfollows:...allthosepressure-containing components ofboilingorpressurized water-cooled nuclearpowerreactorssuchaspressurevessels,'piping,pumpsandvalves,whichare:(1)Partofthereactorcoolantsystem,or(2)Connected tothereactorcoolantsystem,uptoandincluding anyandallofthefollowing:
Theoutermost containment isolation valveinsystempipingwhichpenetrates primaryreactorcontainment, Thesecondoftwovalvesnormallyclosedduringnormalreactoroperation insystempipingwhichdoesnotpenetrate primaryreactorcontainment, Thereactorcoolantsystemsafetyandreliefvalves.Duringthisevent,asmallamountofinventory fromthe1B2SITwasobservedleakingfromaweldassociated withaoneinchvent,-V-3815,locatedonthe1B2safetyinjection pipe,upstreamofthe1B2safetyinjection loopcheckvalve.Pertheabovedefinition, thisventisapartofthereactorcoolantpressureboundarysinceitislocatedonasystemconnected totheRCSandiswithintheoutermost containment isolation valveinsystempipingpenetrating theprimaryreactorcontainment.
Additionally, V-3815islocatedintheQualityGroupAportionofthesafetyinjection system.ThisQualityGroupisdescribed bytheSt.LucieUnit1UpdatedFinalSafetyAnalysisReport(UFSAR),Section3.2,asspecifically applyingtoreactorcoolantpressureboundarycomponents.
TheSt.LucieUnit1TSbasesrelatedtoRCPBleakagespecifythatpressureboundaryleakageofanymagnitude isunacceptable asitmaybeindicative ofimpending furtherpressureboundaryfailure.'herefore, thepresenceofanypressureboundaryleakagerequiresthattheplantbepromptlyplacedinacoldshutdown(Mode5)condition.
Compliance withtheLimitingConditions forOperation (LCO)asspecified intheTechnical Specifications assuresthatthefunctional capability ofequipment requiredforthesafeoperation oftheplantismaintained.
Following theidentification ofpressureboundaryleakageduringthisevent,operators promptlyimplemented theapplicable TSActionrequirements.
NRCFORM366AI4.95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-005-005OF7TEXTllfmorespeceisrequired, useedditianelcopiesoffVRCForm366AJI17IAreviewofsimilardocumented maintenance weldfailuresatSt.Luciewasperformed following theevent.Basedonavailable information, itwasdetermined thatnosignificant failurerateexistedforthisfailuremechanism, therefore thesocketweldleakagefromtheventlineforV-3815isconsidered tobearandomfailure.AsaresultoftheRCBPleakage,nolossofreactorcoolantsysteminv'entory
- occurred, andtheareaofleakagewasisolatedfromtheRCSbythe1Bsafetyinjection headerloopcheckvalve(V-3247)[EIIS:BP:VJ.
V-3247isalsoaddressed bytheSt.LucieUnit1TSandisrequiredtomeetperiodicsurveillance criteriaforleakagewhichprovidesaddedassurance ofvalveintegrity.
Leakagefromthe1B2SITduringtheeventwaslimitedtoapproximately one-halfgallonperminuteandmakeupwasprovidedasnecessary tomaintaintherequiredtankvolume.Theoperability ofthe182Slwasnotaffectedbytheweldleakage.NWithregardtothe1ASDCsystem,St.LucieUnit1UpdatedFinalSafetyAnalysis(UFSAR),Section9.1.5.3.2, statesthat"Nosinglefailureofanactivecomponent duringresidualheatremovalwillresultinalossofcorecoolingcapability.
Thereactorcoolantsystemcanbebroughttorefueling temperature IIsingoneIowpressuresafetyinjection pumpandoneshutdowncoolingheatexchanger."
The1BSDCsystemremainedoperational atalltimesduringthisevent,andwasnotaffectedbytheinoperability ofthe1ASDCtrain.The1BSDCtrainwasplacedinservicetofacilitate theRCScooldownandfunctioned properlyinestablishing Mode5conditions.
TheRCSheatremovalsafetyfunctionwasmaintained atalltimesduringtheevent.Following theevent,FPLengineering personnel performed awalkdownofthe1ASDCsystemandrevieweddataobservedduringeffortstoplacethe1ASDsysteminservice.Basedonthepressures inthesystemobservedduringtheevent,areviewofthedesignandhydrostatic testingforthissystem,andlocalinspection, the1ASDCtrainwasdetermined tobefunctional andacceptable foroperation.
Basedontheabove,thiseventdidnotadversely affecttheprotection ofthehealthandsafetyofthepublic.Following theidentification ofthepressureboundaryleakageonthe182safetyinjection header,St.LucieUnit1wasplacedinColdShutdowninaccordance withtherequirements ofplantTechnical Specifications.
2.Theaffected'!B2safetyinjection headerventlineweldwasremovedandrepairswereimplemented.
TheUnitwasreturnedtoMode1poweroperation onApril23,1997,~following completion oftherepairs.
NRCFORM366AI4-95IILICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-005-006OF7TEXTfifmorespeceisrequired, useadditional copiesofNRCFarm366AJI17I3.Aninspection andfailureanalysiswasperformed forthefailedsocketweldassociated withV-3815ventline.Theanalysisdetermined thattheinitiating failuremechanism ofthesocketweldwashotcracking, duetocontamination oftheweld.Whilethisfailureisconsidered toberandomatSt.Lucie,additional testingwillbedonetoevaluateboricacidweldcontamination anddetermine ifadditional preventive measuresarenecessary tominimizethepotential forrecurrence.
The1ASDCtrainwasreturnedtoservicefollowing systemventingandtherealignment oftheminimumflowrecirculation valveforthe1ALPSIpump.Acautiontagwasplacedontherecirculation valveandaplantworkorderwasinitiated torepairandrestorethevalvetosatisfactory operation.
5.Ventingofthe1ALPSIpumpsuctionlineiscurrently beingperformed atanincreased frequency andtheresultswillbeevaluated todetermine ifadditional changestoventingperiodicity arerequired.
6.Tofurtherprecludethepossibility ofgasformation intheSDCsuctionlines,St.LucieUnit1and2shutdowncoolingsystemprocedures arebeingrevisedtorequirethatsystemventingfollowing SDCoperation beconducted atambienttemperatures.
FPLengineering willreviewtheprocedure revisions forincorporation ofadequateguidanceandcorrective actionspriortoissue.Component:
SafetyInjection Pipe1inchVentLine-SocketWeldMaterial:
Piping-304/316stainless steelwithER308/316fillermaterialSockolet-304stainless steelLER-389/95-001 St.LucieUnit2(2/21/95)
-Theeventdescribes thefailureofalowpressuresafetyinjection (LPSI)pumpduringasurveillance, duetoairbindingofthepump.Therootcausewasattributed tothemigration oftrappedairintheemergency corecoolingsystem(ECCS)headerfollowing maintenance.
In-houseEvent95-09St.LucieUnit1(2/27/95)
-ThiseventinvolvedtheliftingofsafetyreliefvalveV-3483atSt.LucieUnit1following theinitiation offlowfromthe1ALPSIpumpduringSDCoperation.
Theprimarycausewaspressurespikinginthehotlegsuctionlineduetoarapidincreaseinsystemflowratefollowing LPSIpumpstart.Gasvoidingwasconsidered asapossiblecontributor.
Corrective actionswereimplemented following theeventtominimizetransient fluidfloweffects.NKCFORM366AI4.95]
NRCFORM366AI495)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIST.LUCIFUNIT105000335YEARSEQUENTIAL REVISION97-005-007OF7TEXT/ffmorespeceisrequired, useedditionel copiesofiVRCForm388A/I17IBQUB~SAFETYINJECTION TANK(SIT1B2)(SIMPLIFIED DIAGRAM)REFUELING WATERTANKTRETURNHEADER(f--sQi-(LsSIT.;"182~,-.+-(~isLTOSIASCLOSEhs'ROMHPSIPUMPB-eIMIISIASV3815ISSAMPLEAREAOFLEAKAGERCSLOOP182
