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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20148T6101997-07-0303 July 1997 Follow-up to Special Rept SR-96-003-01:on 970411,damage to Cables for Sensors 1A & 1B Discovered.Sensor Cable for 7B Also Found Damaged.Cables for Channels 1A,1B & 7B Found Saturated W/Oil.Sensors Replaced for Channels 1A,1B & 7B ML20148N7281997-06-26026 June 1997 Special Rept SR-97-002-00:on 970513,personnel Identified Design Discrepancy for B CCW Train Radiation Monitor. Design Flaw Existed Since Plant Built.Design Change DC-3537 Approved to Reroute Cooling Water Line from Connection ML20135E9641996-12-10010 December 1996 Special Rept SR-96-003-00:on 961027,valve & Loose Parts Monitoring Sys Declared Inoperable.Caused by Failure of Sensor on Channel 1.Sensor Will Be Replaced During Refueling Outage 8 ML20113E4501996-07-0303 July 1996 Special Rept SR-96-001-00:on 960603,output Breaker for EDG B Failed to Close.Caused by Intermittent Malfunction of Contacts on Synchronizing Switch.Performed Troubleshooting & Replaced EDG B Synchronizing Switch ML20094P5911995-11-27027 November 1995 Special Rept SR-95-004-00:on 951030,EDG Tripped on Turbocharger Low Lube Oil Pressure.Generated Condition Rept 95-1102 ML20094G2031995-11-0808 November 1995 Special Rept SR-95-003-00:on 951010,EDG Experienced Crankcase Overpressurization.Caused by Poor Lubricating Conditions During Startup & Rapid Loading Led to Tin Transfer from Piston to Cylinder Liner ML20093L8421995-10-23023 October 1995 Special Rept SR-95-002-00 on 951011,ABB C-E Identified Leaking Plug Due to build-up of Boric Acided Crystals Around OD of Plug.Leaking Plug Removed by Tig Relaxation & Replaced/Another Rolled Mechanical Plug ML20086E0181995-07-0707 July 1995 Special Rept SR-94-001-01:on 940228 & 0302,EDG a Experienced Nonvalid Failures Due to Worn Mechanical Governor Parts. Mechanical Governor & Faulty Relay Replaced & Procedure OP-009-02, EDG Revised ML20070N6601994-05-0404 May 1994 Special Rept SR-94-003:on 940404,EDG a Experienced Nonvalid Failure While Performing Valid Test.Probably Caused by Emergency Mode Master Run Relay 4EX1 de-energized During Run.Troubleshooting in Progress ML20065A3761994-03-29029 March 1994 Special Rept SR-94-001,on 940228,EDG a Tripped on Overspeed. Caused by Faulty Contacts in Relay of Electronic Grovernor Droop.Faulty Relay & Mechanical Governor Replaced ML20059B9521993-10-26026 October 1993 Special Rept SR-93-001-01,final Rept:On 930811,declared Condenser Vacuum Pump Wide Range Gas Monitor PRM-IRE-002 Inoperable.Monitor Returned to Svc on 930901.Inoperability of Subj Monitor Did Not Pose Safety Concern ML20056H1011993-09-0101 September 1993 Special Rept SR-93-001-00:on 930811,condenser Vacuum Pump WRGM PRM-IRE-002 Declared Inoperable & Not Returned to Svc within Seven Days.Monitor Will Be Returned to Svc After Low Range Sample Flow Cv Repaired & Functionally Checked ML20046D3721993-08-10010 August 1993 Special Rept SR-91-002-03:on 910318,EDG a Experienced Overpressurization.Caused by Gross Cylinder to Cylinder Load Imbalance.Event Classified as Failure Per Reg Guide 1.108.Pulled & Replaced Cylinders ML20126M5881993-01-0606 January 1993 Special Rept SR-92-003:on 921207,EDG a Failed to Reach Rated Speed & Voltage in Less than or Equal to 10 S.Caused by Failure to Properly Secure Turning Gear Brackets.Control Brackets for Turning Gear Interlock Valves Adjusted ML20127M4981992-11-24024 November 1992 Special Rept SR-92-002-00:on 921023,component Cooling Water (CCW) A/B Radiation Monitor Was Inoperable for More than 30 Days.Ts Change Request NPF-38-127,dtd 921021 Submitted,Which Changes Operability Requirement ML20116B2121992-10-23023 October 1992 Special Rept SR-92-001-00:on 921010,inservice Eddy Current Exam of SG Tubing Completed,Per 10CFR50.36(c)(2).Total Number of Tubes Have Been Plugged in SG Shown as Listed ML20086K8731991-12-11011 December 1991 Special Rept SR-91-007-00:on 911111,diesel Generator a Loaded to 4.3 MW & Tripped.Caused by Inadequate Positioning of Turbocharger Inlet Air Butterfly Valve Limit Switch Mounting Bracket.Limit Switch Repositioned ML20086G0201991-11-27027 November 1991 Special Rept SR-91-002-02:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization.Caused by Stuck Piston Rings.Piston & Piston Liner Replaced & Improper Temp Differential Will Be Corrected ML20083D4431991-09-23023 September 1991 Special Rept SR-91-002-01:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization.Caused by Stuck Piston Rings & Improper Temp Differential.Cylinder Liner,Piston Assemblies & Rod Bearings Replaced ML20082U6231991-09-16016 September 1991 Special Rept SR-91-003-01:on 910406,inservice Eddy Current Exam of Facility SG Tubing Completed by Westinghouse.Rept Submitted Per Tech Specs 4.4.4.5 & 6.9.2.Rotating Pancake Coil Exam Results Verified No Detectable Degradation ML20082T2121991-09-13013 September 1991 Special Rept:On 910820,EDG Secured During Surveillance Test Due to Power Dropping Resistor Failure.Power Dropping Resistor Assembly Replaced.Health & Safety of Public & Plant Personnel Not Affected by This Event ML20082C4021991-07-15015 July 1991 Special Rept 91-005-00:on 910619,EDG a Tripped on Turbocharger Lube Oil Low Pressure During Performance of Operating Procedure 903-068.Procedure Changed to Require Lubrication of Turbocharger ML20073Q8001991-05-29029 May 1991 Special Rept SR-91-04-00:on 910429,EDG a Failed Invalidly Due to Spurious Turbocharger Lube Oil Pressure Trip.Edg Restarted.Oil Pressure Remained within Normal Operating Limits & OP-903-068 Completed ML20073B3231991-04-19019 April 1991 Special Rept SR-91-003-00,re 910406 Completion of Inservice Eddy Current Exam of Steam Generator tubing.Follow-up Rept Will Be Submitted by 920406,per Tech Spec 4.4.4.5.b.Total Number of Tubes Plugged in Each Steam Generator Listed ML20084U8591991-04-17017 April 1991 Special Rept SR-91-002-00:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization. Possibly Caused by Improper Temp Differential Between Jacket Cooling Water & Lube Oil Temp.Liner Replaced ML20072Q8931991-03-18018 March 1991 Special Rept SR-91-001-00:on 910207,channel 2 of SPDS Failed & Could Not Be Restored within 7 Days.On 910214, Channel 2 of Qualified SPDS Sensor 8 Out of Svc for More than 7 Days.Channel 2 Probe Will Be Replaced ML20028H8441991-01-25025 January 1991 Special Rept SR-90-004-00:on 901226,emergency Diesel Generator Tripped on Loss of Field While Operating at 100% Power.Caused by Faulty Motor Operated Potentiometer.Faulty Component Replaced ML20065R6021990-12-12012 December 1990 Special Rept SR-90-003-00:on 901112,invalid Failure of Emergency Diesel Generator a Occurred.Caused by Mechanical Failure of 30 Psig Reducer in Control Air Sys & Crack on Spring Cap of Reducer.All Reducers Inspected ML20011F3501990-02-23023 February 1990 Special Rept SR-90-002-00:on 900128,emergency Diesel Generator a Declared Inoperable to Perform Automatic Synchronization Test.Caused by Thick Oil Forming in Low Turbocharge Lube Oil Pressure Sensing Device.Device Cleaned ML20005G7681990-01-12012 January 1990 Special Rept SR-90-001-00:on 891229,condenser Vacuum Pump Wide Range Gas Monitor Inoperable Due to Spurious Alarms. Functional Test Per Maint Instruction (MI)-003-386 Satisfactorily Performed ML20246C9091989-05-0303 May 1989 Special Rept SR-89-001-01:on 890206 & 0403,emergency Diesel Generator a Declared Inoperable.Caused by Fuse Not Being Secured in Fuse Holder & Oxidation of Speed Control Circuit Relay Contacts.Contacts Cleaned & Fuses & Holders Checked ML20245A3951989-04-10010 April 1989 Special Rept SR-88-004-01:on 880420,inservice Eddy Current Exam of Steam Generator Tubing Completed by Westinghouse.Two Tubes Exceeded Plugging Limit in Steam Generator A.All Discrepancies Resolved ML20236B0941989-03-0808 March 1989 Special Rept:On 890206,emergency Diesel Generator Secured Due to Failure of Speed Control Circuit While Generator in Manual Operation.Caused by Oxidation of Relay Contacts in Governor Control Circuitry.Contacts Replaced ML20206H4901988-11-18018 November 1988 Special Rept SR-88-009-00:on 880909,emergency Diesel Generator Tripped Due to Incorrect Valve Lineup.Caused by Personnel Error.Valves Opened ML20151U8841988-08-16016 August 1988 Special Rept SR-88-008-00:on 880726,plant Stack Effluent Accident wide-range Gas Monitor Declared Inoperable.Caused by Pump Failing Step 8.4.2.18 Which Checks high-range Sample Flow within Specified Tolerance.Transmitter Replaced ML20151C1121988-07-15015 July 1988 Special Rept SR-88-007-00:on 880628,primary Meteorological Tower Instruments out-of-svc Greater than Seven Days.Caused by Instruments Being Out of Calibr.Temp Elements Replaced & Corrective Maint on Delta Temp Instruments Completed ML20151C0781988-07-15015 July 1988 Special Rept SR-88-006-00:on 880616,emergency Diesel Generator B Tripped Due to Personnel Error.Caused by Failure to Raise Load within 5 S.Operating Procedure OP-9-002 Reviewed & Considered to Adequately Address Operation ML20195H7171988-06-20020 June 1988 Special Rept SR-88-005-00:on 880511,unit Was in Refueling Mode When Operations Personnel Declared Seismic Monitor SM-IYR-6021 Inoperable.Plastic Lexan Mounting Board Appeared to Be Deformed Due to Heat.Monitor Will Be Relocated ML20153F3831988-05-0404 May 1988 Special Rept SR-88-003-01:on 850801-880404 Several Failures of Emergency Diesel Generators to Start Occurred.Caused by Actuation of Trips Which Bypassed in Emergency Mode.Trip Sensor Replaced ML20153F2541988-05-0404 May 1988 Special Rept SR-88-004-00:on 880420,inservice Eddy Current Exam of Steam Generator Tubing Completed.Rept Submitted in Accordance W/Tech Specs 4.4.4.5.a.Number of Tubes Plugged in Each Steam Generator Listed ML20148F1021988-03-21021 March 1988 Special Rept SR-85-002-01:on 851230,discovered Emergency Diesel Generator a Failed to Complete Surveillance Run as Defined in Procedure OP-903-068 & Tech Spec 4.8.1.1.2a.5. Cause Not Determined.Minor Adjustments Made to Governor ML20148F0971988-03-18018 March 1988 Special Rept SR-88-003-00:from 850801-880308,several Emergency Diesel Generators Failed to Start.Caused by Malfunctioning Trip Mechanisms.Diesels Will Not Be Taken Out of Svc Until Plant Scheduled to Be out-of-svc for Maint ML20149J3411988-02-18018 February 1988 Special Rept SR-88-001-00:on 880128,during Plant Startup Operations,Personnel Declared Fuel Handling Exhaust Wide Range Gas Monitor out-of-svc for Calibr.Caused by Extensive Teardown.Procedure Revised ML20236Q1121987-11-16016 November 1987 Special Rept SR-87-006-00:on 871028,primary Meteorological Tower Upper Wind Speed & Wind Direction Instrument out-of- Svc in Excess of 7 Days.Caused by Failed Signal Converter. Parts Replaced & Instrument Returned to Svc on 871104 ML20236Q2621987-11-13013 November 1987 Special Rept SR-87-005-00:on 871103,Tech Specs 3.3.3.1 & 6.9.2 Violated.Caused by Inoperability of Effluent Accident wide-range Gas Monitor for More than 7 Days Due to Damaged Connectors.New Monitor Should Be Installed by 871125 ML20235J8531987-09-24024 September 1987 Special Rept SR-87-004-00 Re Results of Inservice Eddy Current Exam of Steam Generator Tubing Completed on 861214. No Indication of Degradation Greater than or Equal to 20% Through Wall Detected in Steam Generator a ML20237G9341987-08-21021 August 1987 Special Rept SR-87-003-00:on 870731 & 0809,condenser Vacuum Vacuum Pump Discharge Wide Range Gas Monitor (WRGM) Inoperable.Caused by Water Blockage of Sample Lines.Wrgm Restarted & Being Tested for Operation ML20234B2111987-06-29029 June 1987 Special Rept SR-87-002-00:on 870606,high Range Gas Monitor Inoperable Greater than 7 Days.Caused by Faulty Display Module & Lack of Spares & Quality Documentation.Module Replaced & Monitor Returned to Svc After Functional Test ML20215H0841987-06-17017 June 1987 Special Rept SR-87-001-00:on 870527,during Full Reactor Power,Condenser Vacuum Pump Discharge Wide Range Gas Monitor Declared Inoperable.Caused by Failed Input/Output Circuit Board & Low Range Detector.Faulty Components Replaced ML20205G1731987-03-18018 March 1987 Ro:On 870222,steam Line Break on Scavenging Steam Vent Line from Moisture Separator Reheater Experienced.Caused by Classic Fatigue Failure in Heat Affected Zone of Weld Joining Alloy 800 Matl.Temporary Restraints Added 1997-07-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
- on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B
ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with 05000382/LER-1999-013, :on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included1999-09-23023 September 1999
- on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included
05000382/LER-1999-012-01, :on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With1999-09-13013 September 1999
- on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With
ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With 05000382/LER-1999-011-01, :on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B1999-08-31031 August 1999
- on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B
05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity1999-08-26026 August 1999
- on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity
05000382/LER-1999-009-01, :on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established1999-08-26026 August 1999
- on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established
ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With 05000382/LER-1999-008-01, :on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-021999-07-29029 July 1999
- on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-02
05000382/LER-1999-007-01, :on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff1999-07-23023 July 1999
- on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff
ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With1999-07-14014 July 1999
- on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with 05000382/LER-1999-005-01, :on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested1999-06-24024 June 1999
- on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested
ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20195J9741999-06-16016 June 1999 Safety Evaluation Supporting Amend 152 to License NPF-38 ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195D5491999-06-0303 June 1999 Safety Evaluation Supporting Amend 151 to License NPF-38 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on ABB CE ECCS Performance Evaluation Models 05000382/LER-1999-004-02, :on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing1999-05-14014 May 1999
- on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing
ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20206A9641999-04-21021 April 1999 Safety Evaluation Supporting Amend 150 to License NPF-38 05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With1999-04-0909 April 1999
- on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With
ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired1999-03-25025 March 1999
- on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8151999-02-17017 February 1999 Safety Evaluation Supporting Amend 149 to License NPF-38 ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 05000382/LER-1999-001, :on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With1999-02-0404 February 1999
- on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With
ML20202H9161999-02-0202 February 1999 Safety Evaluation Supporting Amend 148 to License NPF-38 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change 05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With1998-12-31031 December 1998
- on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With
ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20198F4691998-12-21021 December 1998 Safety Evaluation Supporting Amend 147 to License NPF-38 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 1999-09-30
[Table view] |
Text
.. --
M Ent:r y Oper; tion 2, Inc.
btIOf1S Killona, LA 70066 Tel 504 464 3120 1
D. R. Keuter General Manager i
Plaret Operabons
)
Waterford 3 W3F1-95-0180 A4.05 PR
)
November 8,1995 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk j
Washington, D.C.
20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Special Report Gentlemen:
Attached is Special Report Number SR-95-003-00 for Waterford Steam Electric Station Unit 3.
This report outlines the results of the investigation into l
the Emergency Diesel Generator "A" crankcase overpressurization event that 1
occurred on October 10, 1995. The root cause of the overpressurization event was determined to be tin transfer from the SL piston to the cylinder liner. This Special Report is submitted in accordance with Technical Specifications 4.8.1.1.3 and 6.9.2 and USNRC Regulatory Guide 1.108.
Very truly yours, N
Q ch
]
D.R. Keuter General Manager Plant Operations DRK/RTK/tjs Attachment n ~,. m.
9511090301 951108 PDR ADOCK 05000382 g\\ t
(\\
S PDR
=
l
~
l
< Report'ing of Special Report (SR-95-003-00)
W3F1-95-0180 1
Page 2 i
November 8,1995 cc:
L.J. Callan, NRC Region IV, C.P. Patel, NRC-NRR, G.L. Florreich, J.T. Wheelock - INP0 Records Center, R.B. McGehee, N.S. Reynolds, NRC Resident Inspectors Office (WMSB4300), Administrator - LRPD t
SPECIAL REPORT.
SR-95-003-00 REPORTABLE OCCURRENCE On October 10, 1995, Waterford Steam Electric Station Unit 3 was shutdown for the Refuel 7 outage when Emergency Diesel Generator (EDG)
"A" experienced a crankcase overpressurization. The EDG was being run in accordance with Surveillance Procedure OP-903-115 " Train A Integrated Emergency Diesel Generator / Engineering Safety Features Test" when the overpressurization event occurred. This event is classified as a valid failure in accordance with Regulatory Guide 1.108 and is being reported in accordance with Technical Specifications (TS) 4.8.1.1.3 and 6.9.2.
This failure is the first failure in the last 20 valid tests and the fourth failure in the last 100 valid tests.
In accordance with the Waterford 3 Technical Specifications, the currently required surveillance test interval for EDG "A" is at least once per 31 days.
EVENT DESCRIPTION The Refuel 7 outage at Waterford 3 began on September 22, 1995. On September 25, 1995, EDG "A" was removed from service for a routine maintenance outage that included the 18 month inspection required by Inspection Procedure MM-003-015. An exhaust manifold replacement, a fuel pump upgrade, and the removal and reinstallation of three cylinder heads (4R, 5R, SL) were to be performed. The selection of these three heads for removal was based upon the need for maintenance or inspections that required these heads to be removed.
During the period of September 25, 1995, to October 1, 1995, Entergy Operations maintenance personnel from Waterford 3, the River Bend Station, and the Grand Gulf Nuclear Station performed the scheduled maintenance and inspections on EDG "A".
Engineering, maintenance, and vendor personnel (Cooper-Bessemer) utilized the " Inspection Manual for Cooper-Bessemer Model KSV Diesel Engines" to conduct an underside inspection of all 16 cylinder liners. A boroscopic inspection through the removed fuel injector holes of the area of the cylinders above the pistons for those pistons which did not have the heads removed was also performed. The areas of the cylinder liners above the pistons for the 4R, SR, and SL cylinders were also inspected.
Planned maintenance activities were completed on October 1, 1995, and the taggout was cleared in preparation for post maintenance testing.
Several post maintenance starts of EDG "A" were performed for adjustments prior to 1
'releading the EDG to Operations for retesting. On October 8, 1995, EDG "A" was released to Operations for performance of the required Surveillance I
Testing necessary to demonstrate the operability of the EDG. On October 9, i
1995, Surveillance Testing was commenced in accordance with Surveillance Procedure OP-903-115 " Train A Integrated Emergency Diesel Generator / Engineering Safety Features Test". At 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br /> on October 9, 1995, a successful start of the EDG was recorded during the performance of Surveillance Procedure OP-903-115, Section 7.4, " Train A Safety Injection Actuation Test With Offsite Power". However, the EDG was not loaded at i
this time.
On October 10, 1995, Surveillance Procedure OP-903-115 testing was recommenced at Section 7.5, " Train A Safety Injection Actuation Test With Concurrent Loss of Offsite Power". The EDG was started at 1652 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.28586e-4 months <br /> and immediately loaded to approximately 2.6 MW.
For approximately the next hour, EDG "A" continued to run partially loaded in support of the Surveillance Procedure requirements until 1805 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.868025e-4 months <br /> when the EDG was fully loaded to 4.4 MW. At 1806 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87183e-4 months <br /> on October 10, 1995, a full load rejection test was successfully performed per the procedure with the diesel returning to standby operation. At 1821 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.928905e-4 months <br />, EDG "A" was paralleled with offsite l
power and electrical loading of the EDG was once again commenced. By 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br /> on October 10, 1995, the EDG was loaded to 110% (approximately 4.7 MW) and the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run required by Surveillance Procedure OP-903-115, Section 7.6, "24 Hour EDG A Run and Subsequent Loss of Offsite Pcwer Test" was begun.
l At approximately 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br /> on October 10, 1995, Operations and Maintenance personnel in the EDG "A" room heard a muffled " thud" like transient. These personnel observed an immediate issuance of lubricating oil and smoke from the EDG "A" crankcase relief ports. However, no visible flames were abserved. The control room was subsequently contacted, EDG "A" was immediately unloaded and secured, and the Fire Brigade was dispatched.
During an inspection of the EDG performed later that evening, it was determined that the SL piston had failed.
i On October 11, 1995, the SL piston, liner, and articulating rod were removed from EDG "A" and inspected by maintenance, engineering, and EDG vendor (Cooper-Bessemer) personnel.
Extensive damage to both the piston and the liner was observed. An underside inspection was conducted and the 8R liner was observed to exhibit light, vertical scoring on the non-thrust side. As a result of this observation, the 8R piston was pulled and the piston rings were determined to be excessively worn. The cylinder liner was removed and light scoring was visible over the cylinder area traversed by the 6th and 7th piston rings. As a result of the excessively worn piston rings on the 8R piston, it was decided to pull one other piston for inspection. The 6L piston was selected because the piston rings on this 2
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.ipiston had been replaced at the same time as the 8R piston rings. The 6L piston was observed to be in good condition, exhibiting normal wear.
CAUSAL FACTORS Entergy Operations, Inc. believes that the root cause of this event was that poor lubricating conditions during startup and rapid loading led to tin transfer from the piston to.the. cylinder liner. Tin transfer refers to wear or removal of tin plate material from the non-thrust side of the cast iron piston skirt and originates primarily at the skirt upper ridge. The tin is transferred to the chromium-plated cylinder liner surface. The tin deposited on the cylinder liner becomes embedded in the porous surface of the cylinder liner. The embedded tin, often combined with iron wear particles, reduces the porosity of the liner from the Cooper-Bessemer specified 15-25% to some smaller value. The desired porosity is engineered to retain lubricating oil to support lubrication of the piston skirt / cylinder liner interface. With the porosity reduced, the lubricating oil film is reduced or eliminated. This results in increased friction and heat generation, and potentially, piston seizure or a crankcase overpressurization.
Tin transfer is caused by a combination of the following conditions:
Poor lubrication conditions during startup and rapid loading due to draindown of the oil from'the cylinder liner walls during standby is exacerbated by the lower oil control ring which acts to -
remove lubricating oil from the region of high contact stresses discussed below; The sharp edge located at the top of the piston skirt combined with the concave piston skirt shape at low (standby) temperatures presents a relatively small contact area or line contact between J
the piston skirt and the cylinder liner and results in high stresses in this region; and Large lateral forces towards the non-thrust side of the piston which occur during both starting and loading caused by high compression pressures due to leaking or floating of the start air valves during starting and rapid increases in inlet air manifold pressure during rapid loading.
Tin transfer has not been previously observed to progress from non-existent to the advanced stage in the brief period observed at Waterford 3.
The rate at which tin transfer progresses, once initiated, has not been determined.
Prior to this event, it was believed to occur over many hours of operation. This is because tin transfer has been detected in several' stages of progression following long periods of engine operation.
If it were to progress very rapidly, it is unlikely that tin transfer would be identified in the intermediate stages of development.
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EDG "A" was operated for approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> cumulatively following the initial maintenance inspection and prior to the crankcase j
overpressurization event.
However, over this 10 day period, the EDG was started 16 times.
It is plausible to conclude that the number of starts can account for the rapid initiation of the tin transfer observed and that the rapid loading sequences that followed on October 10, 1995, as part of the Technical Specification required Surveillance Testing, could have further propagated the tin transfer to the point of failure.
It is also noted that both crankcase overpressurizations that occurred at Susquehanna l
Steam Electric Station in 1989 and 1990 which were attributed to tin j
transfer occurred under the same circumstances as this event (that is, during the 110% load run).
There have been no indications to date as to why the 5L cylinder was the source of the crankcase overpressurization in lieu of other cylinders. The leakage rate of the start air valves, the magnitude of the concavity of the piston skirt, and quantity of residual lubricating oil are somewhat random.
These effects are directly related to the root cause of the overpressurization event, therefore, the formation of tin transfer is expected to be random as well.
CORRECTIVE MEASURES Condition Report (CR) 95-0962 was generated in accordance with Waterford 3 Administrative. Procedure UNT-006-011, " Condition Report," to provide a means to implement the Waterford 3 Corrective Action Program. The crankcase overpressurization event described in this CR was classified as a significant adverse condition.
Events classified as significant adverse conditions require the preparation of a root cause analysis. The root cause analysis was subsequently prepared by Waterford 3 personnel, The available start evaluation data sheets and running logs were reviewed concurrently with the control room logs and a chronology of events prepared by the Waterford 3 System Engineer for the period October 1, 1995, to October 10, 1995. All recorded parameters and trends were in specification and appeared normal. This includes the log readings that were taken at 2008 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.64044e-4 months <br /> on October 10, 1995, four minutes prior to the crankcase overpressurization.
On October 11, 1995, a sample of the Delvac 1340 lubricating oil was drawn j
from the EDG "A" crankcase sump.
Portions of this sample were sent to three different laboratories for analysis. No abnormalities were identified in any of the analyses.
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< The SL fuel injector was tested by Waterford 3 personnel on October 14, i
1995. This injector was found to be operating within specifications.
The left bank starting air distributor operation was checked by Waterford 3 personnel.
This air distributor was found to be operating properly with the exception that the distributor did not appear to be shutting off air completely to the pilot valve supply lines. The 5L air start valve was also checked and was found to be operating properly. The routing of the 5L pilot valve supply tubing was checked for kinks. No kinks were found in this tubing.
Waterford 3 recently purchased and began to employ the BETA Recip-trap hand held engine analyzer. This engine analyzer system measures cylinder j
pressures, crank angle, and vibration. Due to the newness of this equipment and a need to gain experience in its use, limited data was available regarding EDG "A".
With the assistance of BETA field personnel, previously unanalyzed data collected from a September 12, 1995, EDG "A" run was recovered. Analysis of the data from this run was inconclusive.
The SL piston and cylinder liner were sent to the vendor (Cooper-Bessemer) for inspection. An interim report on the inspection was received by Waterford 3.
The interim report provides specific details on the condition of the piston and liner. On October 12, 1995, Waterford 3 obtained the services of MPR Associates to act as a third party with regard to the root cause of the crankcase overpressurization event. The MPR Associates observations with regard to the 5L piston and liner were essentially the same as the Cooper-Bessemer observations with a few exceptions noted. MPR Associates also inspected the underside of EDG "A" and the 8R piston and cylinder liner at Waterford 3.
It was noted that there were no indications of tin transfer or wear on the lower half of the visible portions of the 14 liners still installed. With regard to the 8R piston and cylinder liner, MPR Associates identified a darkened vertical mark on the non-thrust side of the liner. The mark was diagnosed to be an early phase of tin transfer.
The SL and 8R pistons and cylinder liners have been replaced on EDG "A".
As previously mentioned a vendor inspection of the failed SL piston, articulating rod, and cylinder liner was performed.
The sequence of testing described in section 7.5 of OP-903-ll5 was reviewed. The actual loading sequence that occurred was evaluated to ensure proper precautions are exercised to avoid unnecessary rapid loading during performance of this surveillance. Also, a Technical Specification (TS) change has been submitted which will allow the two hour 110% load test to be performed anytime during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run which is performed every 18 months. Waterford 3 TS currently require this 110% load test to be performed during the first two hours of the 24 test run.
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The lower oil control rings and piston pin end caps have been removed from all EDG "A" and EDG "B" pistons. This should assist in maintaining a lubricating film on the piston skirt / cylinder liner interface and thus reduce the possibility of scuffing and overheating.
Procedure OP-903-068 was revised to specify the performance of the Cooper-Bessemer recommended four hour monthly surveillance runs. The loading sequence for the EDGs was also revised.
During the post maintenance testing of EDG "A" and EDG "B" during Refuel 7, a vibration, crank angle, and firing pressure engine analysis was performed using the BETA engine analysis equipment. The results of this analysis have been evaluated and no significant anomalies were noted.
l An evaluation of a proposed modification to replace the existing EDG governor with a dual program slow start governor will be performed.
In addition, an evaluation of a proposed piston modification will be performed. The modification would alter the profile of the piston skirt to l
a barrel shape during all modes of operation by chamfering the top piston skirt radius and provide a gradual taper transition to the full piston skirt radius, i
Periodic underside inspections of the EDGs to check for the presence of tin transfer will be performed during planned component outages of sufficient duration. The condition of Cooper-Bessemer EDGs throughout the nuclear industry will be monitored through the Cooper-Bessemer Owners Group. This effort will focus on EDGs that have the lower oil control rings and piston pin end caps removed.
SAFETY SIGNIFICANCE Waterford 3 was shutdown for the Refuel 7 outage at the time of this event.
Technical Specifications require that one EDG be operable when the plant is shutdown. The "B" train EDG remained operable throughout the time that EDG "A" was out of service.
In addition, the crankcase relief ports on EDG "A" functioned as designed. Therefore, this event did not compromise the health and safety of the public or plant personnel.
SINILAR EVENTS On March 18, 1991, Waterford 3 was in the Refuel 4 outage when EDG "A" experienced a crankcase overpressurization event while being run in accordance with the prerequisites of the 18 month EDG Inspection Procedure MM-003-015. This crankcase overpressurization event was also initiated in the SL cylinder. The root cause of this Refuel 4 event was the gross 6
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..cylidder to cylinder load imbalance that existed on EDG "A" prior to the Refuel 2 outage.
It is believed that this condition caused an excessive buildup of carbon deposits behind the upper compression rings of piston SL.
Normal deposit accumulation during correct operation of the engine added additional small amounts of carbon deposits that also built up behind the piston rings.
This situation led to the piston rings becoming stuck.
Eventually additional deposits forced the compression rings against the cylinder liner and significantly reduced lubrication. The lack of i
lubrication resulted in increasing the surface temperatures of the piston and liner. As the temperatures increased, the chrome plating on the liner cracked and began spalling off. A piece of chrome plating debris lodged between the piston and the liner. The resulting friction caused the piston 1
area around the debris to become incandescent. This incandescent area ignited the crankcase oil vapor causing the crankcase overpressurization.
1 The root cause of the Refuel 4 outage crankcase overpressurization is not the same as the root cause of the Refuel 7 crankcase overpressurization.
On-site inspection of the piston rings in the SL cylinder on October 11, i
1995, and a subsequent vendor laboratory inspection on October 13, 1995, confirmed that the piston compression rings were not stuck prior to the crankcase overpressurization. These rings were free to move and there was little or no carbon buildup found. The applicability of the corrective actions for the Refuel 4 outage event to preventing the Refuel 7 outage event were reviewed and were found to be not applicable.
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