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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
O I
w e'
Ref:
License No. NPF-38 LOUISIANA /
POWER & LiG HT WATERFORD 3 SES e P. O. BOX B e KILLONA, LA 70066 NINSYS March 21, 1988 W3A88-0024 A4.05 QA U.S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, D.C.
20555
SUBJECT:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Special Report Attached is Special Report Number SR 85-002-01 for the Waterford Steam Electric Station Unit 3.
The Special Report was originally submitted on January 29, 1986 classifying this event as a valid failure.
It has since been learned that the intent of the applicable regulations is to classify only those events which would have resulted in failure of the unit under emergency conditions as valid failures.
This event involved a manual trip due to load sharing oscillations while in parallel with the grid.
Since fine speed control is essential to stable parallel operation it is highly unlikely the observed oscillation would have resulted in the failure of the engine to perform under emergency conditions (i.e.
the EDG alone supplying the bus).
Regulatory Guide 1.108 classifies events wherein the EDG is secured for reasons which would not have resulted in a failure in the emergency mode as invalid tests.
This event is therefore reclassified as an invalid failure and will not be used to determine surveillance frequencies in accordance with Technical Specification 4.8.1.1.2.
Very truly yours, N.S.
Carns Plant Manager - Nuclear NSC/DEBirk 7'
\\
ge032hbs eg?hs2 K O DCD PDF-
"AN EQUAL OPPORTUNITY EMPLOYER" S
Pagn 2 W3A88-0024 March 21, 1988 Attachment cc R.D. Martin, NRC Resident Inspectors Office, INPO Records Center (J.T. Wheelock), E.L. Blake, W.M. Steenson, D.L. Wigginton l
r i
Special Report i
SR-85-002-01 Emergency Diesel Generator A Invalid Failure l
INTRODUCTION At 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> on December 30, 1985, Waterford Steam Electric Station Unit 3 was at 100% reactor power when Plant Engineering personnel discovered that on December 13, 1985, Emergency Diesel Generator A did not satisfactorily complete its surveillance run as defined in procedure OP-903-068, "Emergency Diesel Generator Operability Verification" and Technical Specification 4.8.1.1.2a.5.
The diesel started and loaded properly, however, while in parallel with the grid, it was secured approximately 50 minutes (1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />) later due to load oscillations. The diesel was returned to service at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> on December 14, 1985.
The local representative of the governor manufacturer performed troubleshooting on December 14, 1985, but could not find the cause of the malfunction; however, a few minor adjustments were made to the governor.
The subsequent performance of the diesel has been satisfactory. This manual diesel shutdown resulted from i
load sharing oscillations while in parallel with the grid. This would not have resulted in a failure of the diesel under emergency conditions since the diesel is the sole source of power to its respective loads in the emergency made.
This event is therefore not considered a valid test or failure.
There have been no failures of this diesel in 81 start attempts. The testing frequency remains once per 31 days.
NARRATIVE At 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> on December 30, 1985, Waterford Steam Electric Station Unit 3 was at 100% reactor power when Plant Engineering personnel discovered that on 1
December 13, 1985 (while in mode 5) Emergency Diesel Generator A did not satisfactorily complete its surveillance run as defined in procedure i
OP-903-068, "Emergency Diesel Generator Operability Verification" and Technical l
Specification 4.8.1.1.2a.5.
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i The diesel was manually started at approximately 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br /> on December 13, 1985. The diesel performed satisfactorily in parallel with the grid until approximately 50 minutes later when the load began to fluctuate resulting in the manual termination of the test.
Therefore, the diesel did not complete the 60 minute. test run as required by Technical Specification 4.8.1.1.2a.5.
Emergency Diesel Generator A was declared inoperable at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br /> on December 13, 1985. This manual diesel shutdown resulted from load sharing oscillations while in parallel with the grid. This would not have resulted in a failure of the diesel under emergency conditions since the diesel is the sole source of power for its respective loads in the emergency mode. This event is therefore not considered a valid test or failure. There have been no failures of this diesel in 81 start attempts.
CORRECTIVE ACTION 4
The local representative of the governor manufacturer (Woodward Governor Company) was on site December 14, 1985, in order to assist in troubleshooting the governor valve. Although maintenance personnel could not determine any specific reason for the governor valve fluctuations (or hunting), minor adjustments were made to the governor amplifier stability and gain potentiometer.
Upon completion of its surveillance run, Emergency Diesel Generator A was returned to service at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> on December 14, 1985.
PLANT CONTACT D.W. Vinci, Maintenance Superintendent, 504/464-3138.
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