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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 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 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 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 W3P87-0237, Suppl 1 to Special Rept SR-85-001:on 850916,seismic Monitor Mounted on Pressurizer Found Damaged & Inoperable.Relocation of Seismic Monitor Completed,But Tech Spec Not Yet Approved1987-01-19019 January 1987 Suppl 1 to Special Rept SR-85-001:on 850916,seismic Monitor Mounted on Pressurizer Found Damaged & Inoperable.Relocation of Seismic Monitor Completed,But Tech Spec Not Yet Approved ML20214V2821986-09-26026 September 1986 Special Rept SR-86-005-00:on 860909 & 17,secondary & Primary Towers Removed from Svc,Respectively,But Not Returned to Svc within 7 Days.Caused by Need to Replace Hoist Cables. Secondary Tower Returned to Svc on 860916 ML20206J6331986-06-20020 June 1986 Special Rept SR-86-004-00:on 860523,emergency Diesel Generator a Malfunctioned.Caused by Failure of Power Parallel Voltage Dropping Resistor in Electrical Governor Control Circuit.Power Resistors & Amplifier Replaced ML20211H3531986-06-13013 June 1986 Special Rept SR-86-003-00:on 860523,wide-range Gas Monitor PRM-JR-0110 Declared Inoperable.Caused by Performance of Functional Test Per Procedure MI-3-382.Check Valve Removed & Seat Reworked.Monitor Returned to Svc on 860604 1997-07-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With 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 ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) 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 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 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 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 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 ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 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 ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With 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 ML20195E5161998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Waterford 3.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K0801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with ML20151W8331998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with ML20237B6831998-08-17017 August 1998 LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 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 ML20237B5261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Waterford 3 ML20236S9031998-07-22022 July 1998 SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3 ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20236N4181998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Waterford,Unit 3 ML20248E7781998-06-0101 June 1998 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20249A4711998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Waterford 3 Ses ML20196A4051998-05-31031 May 1998 Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20247F6761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/ ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216B1751998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Waterford 3 Ses ML20217M1411998-03-0303 March 1998 Rev 2 of Waterford 3 Cycle 9 Colr 1999-09-30
[Table view] |
Text
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Entergy Operations, Inc.
_- p9Y r o nm e Operations o u^'m Tel W i.% ) 3120 j
__ .. L.__ _ _.___ _._... _ . . . _ _ . . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . - . _ . _ _ . . _ _ . . _ _ _ _ . _ - _ _ _ _ _ _ _ _ .
D.F. Packer p : i. n . . e ;. r
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W3F1-94-0048 A4.05 i PR May 4, 1994 l
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 l Reporting of Special Report ;
Gentlemen: i Attached is Special Report Number SR-94-003-00 for Waterford Steam Electric Station Unit 3. 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, yhf I
D.F. Packer General Manager - Plant Operations DFP/CJT/tjs Attachment cc: L.J. Callen, NRC Region IV G.L florreich J.T. Wheelock - INP0 Records Center R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office g:
Administrator - LRPD /
05007n 9405090061 940504 PDR
\\
ADOCK 05000382 S PDR
, 'i i -
j 1
SPECIAL REPORT SR-94-003 4
REPORTABLE OCCURRENCE At 0023 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> on April 4, 1994, Emergency Diesel Generator (EDG) 'A' experienced a nonvalid failure while performing a valid test. At 1654 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.29347e-4 months <br /> that same day, EDG 'A' experienced a second nonvalid failure while troubleshooting for the failure that occurred at 0023 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />. Pursuant to Technical Specification (TS) 4.8.1.1.3, all diesel generator failures, valid or nonvalid, shall be reported in a Special Report to the Commission
. pursuant to Specification 6.9.2 within 30 days.
INITIAL CONDITIONS Plant Power: 0%
Plant Operating Mode: Mode 6; Refueling Procedures Being Performed Specific to this Event:
OP-009-002, " Emergency Diesel Generator" OP-903-115, " Train A Integrated Emergency Diesel Generator / Engineering Safety Features Test."
Technical Specification LCO's in Effect Specific to This Event: None Major Equipment Out of Service Specific to this Event:
Emergency Diesel Generator 'A' EVENT DESCRIPTION During the Refuel 6 Outage, EDG 'A' was inoperable for maintenance from 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> on March 24, 1994, to 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br /> on April 9, 1994. During that time, EDG 'A' experienced two nonvalid failures.
The first nonvalid failure occurred during the performance of a valid test. At 2359 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.975995e-4 months <br /> on Acril 3, 1994, EDG 'A' was automatically started and loaded to implement Section 7.5 of OP-903-115. Section 7.5, " Train A )
Safety Injection Actuation Test With Concu' rent loss of Off Site Power," I is performed at least cnce per 18 months while shutdown to demonstrate diesel operability in accordance with TS requirements.
During the test two conditions were noted. After depressing and holding the emergency stop push button, test personnel noticed that Fuel 011 l Solenoid 20F01 was not energized as expected. Also, prior to closing Safety Bus 3A3-S to 3A2 tie breaker 4KVEBKR3A 11, the diesel start light on the Control Room EDG Control Panel operating switch was not illuminated. This switch was illuminated during the initial start. l l
I l
1 l
I i
After operating at load for approximately 17 minutes, EDG 'A' tripped at 0023 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> while paralleling to offsite power. There was no annunciation ,
at the time of the trip to indicate its cause. The trip occurred when the diesel transferred from the emergency operating mode to the test mode.
This transfer is concurrent with the closure of Safety Bus 3A3-S to 3A2
- tie breaker 4KVEBKR3A 11. The OP-009-002 Start Evaluation Sheet generated for the event categorized the trip as a nonvalid failure pursuant to Position 2.e.(2) of Regulatory Guide 1.108, 4
A definite root cause of the failure could not be determined. However, l the most probable cause of the failure is that Emergency Mode Master Run Relay 4EX1 was de-energized at some point during the diesel run. This would explain de-energization of Fuel Oil Solenoid 20F01. The 20F01 solenoid would have de-energized immediately upon de-energization of 4EXI.
Because the 4EX1 relay was not operating at the time the emergency stop push button was depressed, Unit Master Run Relays 4X1, 4X2 and 4X3 (relays not required in Emergency Mode) would have de-energized. Consequently, the Control Room EDG Start /Stop control switch start lamp and Engine Shut Down Solenoid 20SD would have de-energized. Solenoid 20SD remains by-passed in Emergency Mode by two Emergency Mode Master Run Relays --
4EX2 and 4EX5. However, as a result of Solenoid 20SD being de-energized, EDG 'A' would have tripped when it transferred to the test mode with no indication of why the trip occurred.
Immediately after the trip, pertinent circuits were checked for loose connections. No loose connections were identified. A Work Authorization (WA) was prepared to troubleshoot Fuel Oil Solenoid 20F01 and those components that may have caused the nonvalid failure. Troubleshooting was conducted during a simulated start (i.e., Overspeed Trip, Field Flash Breaker, and Starting Air isolated) and an Engineered Safety Features Actuation Signal (ESFAS) Test Module start. Pertinent relays and solenoid coils were monitored during that time and verified to be functioning satisfactorily. No problems were identified with the Control Room EDG Control Panel operating switch, nor with the 20F01 and 20F02 Fuel Oil Solenoids.
Subsequent to the ESFAS start, it was decided to continue troubleshooting by paralleling to offsite power. While attempting to parallel to offsite power, EDG 'A' tripped in the test mode at 1654 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.29347e-4 months <br />. The EDG Local Annunciator Panel gave indication of a reverse power trip. Also, the reverse power relay was verified tripped. The OP-009-002 Start Evaluation Sheet generated for the event categorized the trip as a nonvalid failure pursuant to Position 2.e.(7) of Regulatory Guide 1.108, 2 e
~. . -. . . . . . ..
j .
l CORRECTIVE MEASURES In addition to troubleshooting, Section 7.6 of OP-903-115, "24-Hour EDG A Run And Subsequent Loss of Offsite Power Test," wr ruccessfully completed on April 5, 1994 at approximately 2052 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.80786e-4 months <br />. If the conditions that i
caused the first nonvalid failure had existed during this test, then a l similar failure would have occurred. This is due to the fact that EDG 'A' 2 was paralleled to offsite power in the same manner as was done while implementing Section 7.5 of that procedure. Although the 4EX1 relay was
! operating satisfactorily during the troubleshooting, a Condition l
Identification has been initiated to replace this relay during the next
- scheduled EDG 'A' maintenance outage.
1 Additional troubleshooting will be conducted to investigate the cause of
- the reverse power trip. A Condition Identification has been written to i connect recorders and monitur EDG 'A' parameters during future ESFAS Test j Module starts. This corrective measure is being conducted as part of an i investigation into an earlier reverse power trip. Special Report SR j 001-00 reported an event that occurred on March 2, 1994, when EDG 'A' i tripped on reverse power while paralleling to offsite power. The investigation into that event will continue and corrective measures will
- be taken as appropriate.
1 SAFETY SIGNIFICANCE The first nonvalid failure occurred when the diesel transferred from the
- emergency operating mode to the test mode. This transfer is concurrent with the closure of Safety Bus 3A3-S to 3A2 tie breaker 4KVEBKR3A 11. The
- components that would cause this type of failure are bypassed in the emergency operating mode.
I
) The second nonvalid failure also occurred in the test mode. Reverse power i trips have no impact on the emergency mode of operation. In the emergency mode, the diesel is energizing an isolated safety bus. Reverse power trip 1 will be locked out of the diesel shutdown circuitry for the duration of an f emergency event and will not be enabled until normal offsite power is restored to the safety bus.
Neither of the nonvalid failures would have affected emergency mode operation. As a result, these events did not compromise the health :nd j safety of the public. Furthermore, EDG 'B' was operable throughout the
- time EDG ' A' was unavailable.
- In accordance with Regul&tcry Guide 1.108, the current surveillance test interval for EDG ' A' is 31 days. This test interval is in accordance with j
the schedule of Regulatory Position C.2.d.
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SIMILAR EVENTS No previous events similar to the first nonvalid failure were identified.
- However, as stated previously, Special Report SR-94-001-00 reported an event similar to the second nonvalid failure in that EDG 'A' tripped on reverse power while paralleling to offsite power. This event occurred on i March 2, 1994.
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