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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARNRC-97-0076, Ro:On 970703,seismic Monitoring Instrumentation Sys Was Declared Inoperable.Seismic Instrumentation Was Not Located in RHR Complex Pump Room as Described in Ts.De Intends to Restore Instruments to Operable Status1997-08-0808 August 1997 Ro:On 970703,seismic Monitoring Instrumentation Sys Was Declared Inoperable.Seismic Instrumentation Was Not Located in RHR Complex Pump Room as Described in Ts.De Intends to Restore Instruments to Operable Status NRC-97-0056, Special Rept:On 970319,disconnect Switch for MCC 72E-5A, Position 3CR Opened Unexpectedly & Would Not Reclose When Rotary Actuator Placed in on Position.Caused by Inadequate Preventive Maint.Cleaned & Relubricated Disconnect Switches1997-05-0505 May 1997 Special Rept:On 970319,disconnect Switch for MCC 72E-5A, Position 3CR Opened Unexpectedly & Would Not Reclose When Rotary Actuator Placed in on Position.Caused by Inadequate Preventive Maint.Cleaned & Relubricated Disconnect Switches NRC-96-0089, Special Rept:On 960917,high Pressure Switch Could Not Be Satisfactorily Calibr.Existing Pressure Switch Was Removed & New Switch Installed1996-10-17017 October 1996 Special Rept:On 960917,high Pressure Switch Could Not Be Satisfactorily Calibr.Existing Pressure Switch Was Removed & New Switch Installed NRC-96-0053, Special Rept:Documents Inoperability of Seismic Monitoring Instrumentation Exceeding 30 Days.Caused by Inadequate Surveillance Testing of Active Triaxial Accelerometers & Seismic Trigger.Surveillance Procedures Will Be Revised1996-05-24024 May 1996 Special Rept:Documents Inoperability of Seismic Monitoring Instrumentation Exceeding 30 Days.Caused by Inadequate Surveillance Testing of Active Triaxial Accelerometers & Seismic Trigger.Surveillance Procedures Will Be Revised NRC-96-0012, Special Rept:On 960109,debonded & Damaged Control Ctr HVAC Duct Sealant Found.Areas of Debonded & Damaged Sealant Repaired1996-01-23023 January 1996 Special Rept:On 960109,debonded & Damaged Control Ctr HVAC Duct Sealant Found.Areas of Debonded & Damaged Sealant Repaired NRC-94-0046, Special Rept:On 940622,re Emergency Diesel Generator Test Failure.Troubleshooting Performed Into Cause.Vertical Drive Spring Pack Was Cleaned & Rebuilt Using New Springs & Wear Plates1994-07-22022 July 1994 Special Rept:On 940622,re Emergency Diesel Generator Test Failure.Troubleshooting Performed Into Cause.Vertical Drive Spring Pack Was Cleaned & Rebuilt Using New Springs & Wear Plates NRC-93-0153, Ro:On 931216 Failure of EDG 13 Occurred.Fuel Rack Linkage Found Disconnected During Troubleshooting.Caused by Clamp Bolt Coming Loose.Investigation of Why Bolt Came Loose in Progress.Engine Shut Down & Fuel Rack Linkage Reconnected1994-01-14014 January 1994 Ro:On 931216 Failure of EDG 13 Occurred.Fuel Rack Linkage Found Disconnected During Troubleshooting.Caused by Clamp Bolt Coming Loose.Investigation of Why Bolt Came Loose in Progress.Engine Shut Down & Fuel Rack Linkage Reconnected 05000341/LER-1993-014, Special Rept:On 931225,plant Experienced Failure of Turbine Generator,Resulting in Reactor Scram.Info Collected from Seismic Monitoring Instrumentation Still Being Evaluated. Event Will Also Be Addressed in LER 93-0141994-01-0404 January 1994 Special Rept:On 931225,plant Experienced Failure of Turbine Generator,Resulting in Reactor Scram.Info Collected from Seismic Monitoring Instrumentation Still Being Evaluated. Event Will Also Be Addressed in LER 93-014 NRC-93-0121, Special Rept:On 930813,ECCS Injection Occurred When Instrument Calibr/Vent Isolation Valve Inadvertently Unseated.Injection Terminated When HPCI Automatically Tripped Off When Water Level Reached High Water Level 81993-11-11011 November 1993 Special Rept:On 930813,ECCS Injection Occurred When Instrument Calibr/Vent Isolation Valve Inadvertently Unseated.Injection Terminated When HPCI Automatically Tripped Off When Water Level Reached High Water Level 8 NRC-89-0026, Special Rept:On 890127,active Seismic Monitor Playback Unit Taken Out of Svc for Routine Channel Calibr,Resulting in Seismic Monitoring Sys Being Inoperable for 30 Days.Caused by Failure of Unit Drive Motor.New Sys Being Evaluated1989-03-0808 March 1989 Special Rept:On 890127,active Seismic Monitor Playback Unit Taken Out of Svc for Routine Channel Calibr,Resulting in Seismic Monitoring Sys Being Inoperable for 30 Days.Caused by Failure of Unit Drive Motor.New Sys Being Evaluated NRC-88-0134, Special Rept:On 880527,div II Standby Gas Treatment Radiation Exhaust Accident Range Monitor Process Controller Discovered Switching Between Normal & Standby Modes & Declared Inoperable.Caused by Problem in 8K Board1988-06-10010 June 1988 Special Rept:On 880527,div II Standby Gas Treatment Radiation Exhaust Accident Range Monitor Process Controller Discovered Switching Between Normal & Standby Modes & Declared Inoperable.Caused by Problem in 8K Board NRC-88-0126, Ro:On 880425,emergency Diesel Generator Start Failure Occurred.Caused by Intermittent Failure of K1 Contact or reset.K1 Contactor Assembly,Including Attached Auxiliary Contacts Replaced1988-05-25025 May 1988 Ro:On 880425,emergency Diesel Generator Start Failure Occurred.Caused by Intermittent Failure of K1 Contact or reset.K1 Contactor Assembly,Including Attached Auxiliary Contacts Replaced NRC-88-0124, Ro:On 880420,emergency Diesel Generator (EDG) 13 Start Failure Occurred.Caused by Improper Setting of EDG 13 Woodward Generator Actuator Load Limit Knob by Unauthorized Person.Edg Unloaded & Load Limit Knob Set to Max1988-05-20020 May 1988 Ro:On 880420,emergency Diesel Generator (EDG) 13 Start Failure Occurred.Caused by Improper Setting of EDG 13 Woodward Generator Actuator Load Limit Knob by Unauthorized Person.Edg Unloaded & Load Limit Knob Set to Max 05000341/LER-1988-004, Special Rept:On 880110,ECCS Actuation Occurred.Operator Manually Tripped Sys.Details of Event Discussed in LER 88-0041988-04-11011 April 1988 Special Rept:On 880110,ECCS Actuation Occurred.Operator Manually Tripped Sys.Details of Event Discussed in LER 88-004 NRC-87-0189, Ro:On 870926,emergency Diesel Generator Failed to Start. Caused by Inadvertent Closure of Instrument Isolation Valve. Instrumentation & Controls Repairman Involved Will Be Counseled1987-10-26026 October 1987 Ro:On 870926,emergency Diesel Generator Failed to Start. Caused by Inadvertent Closure of Instrument Isolation Valve. Instrumentation & Controls Repairman Involved Will Be Counseled NRC-87-0160, Ro:On 870905,start Failure of Emergency Diesel Generator 13 Occurred During Invalid Test.Caused by Emergency Diesel Generator Tripping on Low Fuel Oil Pressure During Monthly Surveillance Slow Start & Load Test.Personnel Counseled1987-10-0505 October 1987 Ro:On 870905,start Failure of Emergency Diesel Generator 13 Occurred During Invalid Test.Caused by Emergency Diesel Generator Tripping on Low Fuel Oil Pressure During Monthly Surveillance Slow Start & Load Test.Personnel Counseled NRC-87-0113, Ro:On 870625,emergency Diesel Generators (Edgs) 12,13, & 14 Automatically Started Simultaneously Due to ESF Actuation Signal.Edgs 12 & 14 Synchronized & Loaded Successfully.Edg 1 Trouble Alarm Annuciated.Cause Unknown1987-07-25025 July 1987 Ro:On 870625,emergency Diesel Generators (Edgs) 12,13, & 14 Automatically Started Simultaneously Due to ESF Actuation Signal.Edgs 12 & 14 Synchronized & Loaded Successfully.Edg 1 Trouble Alarm Annuciated.Cause Unknown NRC-87-0088, Revised Ro:On 870130,start Failure of Emergency Diesel Generator (EDG) 14 Occurred During Monthly Surveillance Tests.History Folders for EDG Signal Generator Revised to Include Caution Sheet & Installation Check Encls1987-06-22022 June 1987 Revised Ro:On 870130,start Failure of Emergency Diesel Generator (EDG) 14 Occurred During Monthly Surveillance Tests.History Folders for EDG Signal Generator Revised to Include Caution Sheet & Installation Check Encls NRC-87-0070, Ro:On 870223,reactor Shut Down as Result of Inoperable HPCI, Per Tech Spec 3/4.5.1.HPCI Sys Restored to Operable Status. NRC Informed After Commencement of Shutdown.Unusual Event Should Have Been Declared When Shutdown Initiated1987-05-20020 May 1987 Ro:On 870223,reactor Shut Down as Result of Inoperable HPCI, Per Tech Spec 3/4.5.1.HPCI Sys Restored to Operable Status. NRC Informed After Commencement of Shutdown.Unusual Event Should Have Been Declared When Shutdown Initiated ML20212E9441987-02-27027 February 1987 Ro:On 870130,during Valid Testing Following Issuance of OL, Start Failure of Emergency Diesel Generator 14 Occurred. Caused by Disengaged Camshaft During Start String Check. Output Relay Adjusted Back Into Tolerance ML20211P5921987-02-20020 February 1987 Ro:On 870123,start Failure Occurred During Testing of Emergency Diesel Generator 13.Caused by Personnel Failure to Reset Exciter Trip & Autostart Buttons After Setpoint Adjustment of Jacket Coolant Pressure Switch ML20207N5621987-01-12012 January 1987 Ro:On 861117,condensate Storage Tank (CST) Spilled.Caused by Insufficient Overpressure Protection on Hpci/Rcic Test Line, in Combination W/Sequencing of Valves.Electrical Interlocks Installed to Preclude Simultaneously Closing CST Valves ML20207P5541987-01-12012 January 1987 Ro:On 861213,emergency Diesel Generator 14 Failed to Start During Invalid Tests.Caused by High Coolant Pressure Low Alarm Setpoint & Low Coolant Pressure Switch Setpoint. Setpoints Revised ML20211P7021986-12-12012 December 1986 Ro:On 861114,emergency Diesel Generator Failed During Fast Start Surveillance Test.Caused by Insufficient Jacket Water Coolant Pressure to Close Cpla Pressure Switch.Cpla Pressure Switch Setpoint Revised ML20214V0881986-11-26026 November 1986 Ro:On 861031,start Failure Occurred on Emergency Diesel Generator 14.Caused by Personnel Closing Cabinet Door Resulting in Voltage Spike Due to Reorientation of Leads. Personnel Counseled ML20212H5061986-08-0707 August 1986 Ro:On 860708 & 09,start Failures of Emergency Diesel Generator 14 Occurred.Caused by Air in Fuel Lines & Personnel Error by Not Resetting Exciter.Fuel Oil Sys Purged & Personnel Educated Re Correct Procedures ML20137L6211986-01-15015 January 1986 Ro:On 851217,emergency Diesel Generator 13 Failed to Start. Caused by Failure of Procedure Used to Start Generator & Increase Engine Speed to Specifically Require Max Setting of Mechanical Governor.Procedures Modified ML20137L5401986-01-13013 January 1986 Ro:On 851214,emergency Diesel Generator 13 Tripped on Low Lube Oil Pressure During Slow Start of Engine.Caused by Starting Engine & Idling at 400 Rpm W/Lube Oil Warmer than Normal.Mod Allowing Slow Start Capability Installed ML20128G2631985-06-21021 June 1985 Ro:On 850606,surface Covering Source Seal Scratched, Permitting Contamination by Fe-55.Employee Hands & Trousers Contaminated.Employee Decontaminated to Less than 100 Cpm & Trousers Confiscated 1997-08-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20197A9921997-12-15015 December 1997 Rev 0 to Efp,Unit 1 Fermi 1 Sar NRC-97-0131, Monthly Operating Rept for Nov 1997 for Fermi 21997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Fermi 2 ML20248H1151997-10-31031 October 1997 Rev 1 to Colr,Cycle 6 for Fermi 2 1999-09-30
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Om3 Robert S. Lenart Plant Mzmager Fermi-2 Edison EEE** 1 r a:1.
August 7, 1986 NP860387 PRIORITY ROUTING bb Ekd*"
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6 Mr. Jamcc G. Koppler Regional Administrator Q-na Region III FILM-U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Emergency Diesel Generator Start Failures Please find enclosed our report on two start failures of Emergency Diesel Generator (EDG) 14 on July 8 and 9, 1986.
These start failures were determined to be invalid tests as defined in NRC Regulatory Guide 1.108, Section C.2.e. This report is submitted to you in accordance with Fermi 2 Technical Specification 4.8.1.1.3 and 6.9.2.
- If you have any questions regarding this report, please contact Mr. Lewis Bregni, Compliance Engineer at (313) 586-5313.
l Sincerely,
/
u~V 1
cc: M. D. Lynch l
W. G. Rogers yQ l
G. C. Wright USNRC Document Control Desk
' l l Washington, D. C. 20555 8608140088 860807
{DR ADOCK 05000341 PDR AUG 1119E t
e-Mr. James G. Keppler August 7, 1986 NP860387
.Page 2
-ENCLOSURE 1 Emergency Diesel Generator Start Failures
- 1. Emergency Diesel Generator Involved:
EDG 14
- 2. Identification of Failures:
Failure Dates: July 8, 1986, 2138 hrs July 9, 1986, 1826 hrs
Description:
These were the first and second start failures of EDG 14 since issuance of the Fermi-2 operating license (OL). Before these two start failures, there had been twenty (20) previous valid test starts since the OL was issued. The July 8 and 9 start failures are considered failures in invalid tests under Section C.2.e of NRC Regulatory Guide 1.108, primarily because operating error was involved in both start failures. In addition, the July 9 start failure involved failure to reset the exciter, a feature automatically reset during emergency starts.
- 3. Cause of Failures:
3.a. July 8 Start Failure EDG 14 had been out of service for approximately two weeks prior to July 8, 1986 for maintenance surveillances required every eighteen months by Fermi-2 Technical Specifications. Post-maintenance testing required a fast-start of the EDG.
The EDG air start system commenced its startup cycle, but the EDG tripped on a " start failure" approximately seven seconds after the start signal was initiated. The trip was initiated by the timing relay which terminates a diesel start if the EDG does not achieve 250 RPM within seven seconds after a start signal.
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9 Mr. James G. Keppler August 7, 1986 NP860387 Page 3 During the 18-month surveillance, Maintenance personnel had performed work on EDG 14's fuel oil system. This work introduced air into the fuel oil system at the two fuel oil filters and at the tubing between the injector pumps and the injectors. During the annual' preventive maintenance (performed at the same time), air was also introduced at the strainers to the engine-driven fuel oil pump, the motor driven fuel oil pump, and both fuel oil transfer pumps.
The fuel lines must be refilled with fuel before the EDG is restarted. Plant Technical personnel informed the Nuclear Shift Supervisor (NSS) that the EDG fuel oil system had to be purged and primed before starting the EDG. The NSS was informed that it was necessary to run the motor-driven standby fuel oil pump (SFOP) until the fuel oil pressure stabilized and to run the pump for one minute after starting the EDG.
At shift turnover, the offgoing NSS did not communicate this to the oncoming NSS. The oncoming shift ran the motor-driven SFOP for 5-10 minutes, but turned it off before starting the EDG. Running the motor-driven SFOP circulates fuel through the fuel oil system and back to the fuel oil day tank. Air upstream of the engine driven pump is not purged by this method. The fuel filter also was not vented.
When the EDG was given a start signal, the starting air system rolled the engine, but the engine failed to achieve sufficient speed in the first seven seconds because air in i the fuel lines prevented normal flow of fuel to the cylinders. The motor-driven SFOP did not purge the air l and provide pressure on the fuel header before the l
cranking time control relay timed-out. This sequence of events was confirmed by contact with the EDG vendor representative.
The operator at the EDG local control panel was then I informed that the motor-driven SFOP needed to be operated j prior to starting the engine and for one minute after I startup. Subsequently, the local operator ran the SFOP as prescribed and the EDG started correctly.
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Mr. James G. Keppler August 7, 1986 NP860387 Page 4 During starts of the other EDGs, the SFOP was run prior to and after the EDG start signal was initiated. The other EDGs started succescfully after their l maintance/ surveillance outages, verifying that there was ;
no problem with air in their fuel systems.
The root cause of the July 8 start failure of EDG 14 was an insufficient purge and prime of the fuel oil system after maintenance. This failure would not have occurred if the operator at the EDG had received proper information from the previous shift regarding operation of the I motor-driven SFOP during the engine start. Because of this human error, this start failure is considered an invalid test.
3.b. July 9 Start Failure EDG 14 tripped on " field failure" during a fast start surveillance test on July 9 at 1826 hrs. The EDG was fast started from the local control panel and was operating at nominal speed (900 RPM) for appproximately 30 seconds before it tripped on " field failure". The EDG tripped on
" field failure" because there was no excitation or field voltage. After communicating with personnel in the main Control Room, the operator at the EDG immediately realized that the exciter had not been reset after the previous engine run.
The exciter should have been manually reset during the EDG shutdown immediately preceding the start attempt. In addition, the operator should have verified exciter reset during the prerequisites for the surveillance run. In this event, the exciter was left tripped. As a result, the time delay relay (40A) tripped EDG 14 approximately 30 seconds after the engine started because no excitation voltage developed across the generator field. After the trip, the local operator manually reset the exciter. The EDG was then started successfully.
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Mr. James G. Keppler August 7, 1986 NP860387 Page 5 At present'there is no indication at the EDG local control
-panels to inform the operator that the exciter is not reset.- However,. there are;two-alarms in the Control Room which indicate the exciter is not reset. During planned
" slow" starts, the two Control Room alarms ("Div II EDG 14 Exciter Trip", Annunciator 10D12; and "Div II EDG 14 Not Ready For Auto Start", Annunciator 10D8) are present because the exciter remains shutdown until engine speed reaches 900 RPM. The EDG procedure (24.307.17, "EDG 14 Start and Load Test") requires the operator to verify that there are no alarms present at the local EDG control panel or in the Control Room before starting the EDG.
Investigation of this event revealed that the Control Room Nuclear Supervising Operator (NSO) observed the " Exciter Trip" alarm and the "EDG Not Ready For Auto Start" alarm were annunciating in the Control Room before the attempt to start EDG 14. Per procedure, the local operator at the EDG control panel verified that no alarms were present at his panel.
Per procedure, the Control Room NSO informed the local operator that no " abnormal" alarms were present in the Control Room. The Control Room NSO thought that test i personnel were preparing for a slow start as originally l planned. Unbeknownst to him, plant Technical personnel had decided to repeat the " fast" start portion of j procedure to verify the results of the previous l surveillance run. -The Control Room NSO thought a " slow" start was underway. The slow start in performed using a different Attachment to the same procedure, 24.307.17.
The Control Room NSO expected to see the two alarms which l were present in the main Control Room during a " slow" l
start. Thus, the exciter remained deenergized when the EDG l
start signal was given. This led to the EDG trip on field i failure.
l The July 9, 1986 start failure on EDG 14 is considered an
, " invalid test" start failure under Regulatory Guide 1.108 because:
(1) The circuit logic for the EDG would have automatically reset the exciter if an emergency start signal had been received. Also, the field failure trip is bypassed during emergency starts.
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Mr. James G. Keppler August 7, 1986 NP860387 Page 0 I
i I
(2) The miscommunication between the Control Room NSO and '
test personnel was the result of human error. Personnel involved in the test erred in not ensuring that all participants acknowledged that a " fast" start was being undertaken.
4.a. Corrective Measures Taken For the July 8, 1986 Start Failure l The maintenance procedure for work on the EDG fuel system is being revised to require the fuel system to be vented -
and purged of air after maintenance on the fuel system.
In addition, plant procedures will be revised to require a "no-credit" run of the engine (considered troubleshooting
, and, therefore, not a valid test, under Regulatory Guide 1.108, Section C.2.e.7) after maintenance on the fuel system. This will include operating the motor-driven SFOP until the fuel oil pressure stabilizes (usually about five minutes) before starting the engine, and will include running the SFOP for one minute after starting the engine. After completion of the "no-credit" run, the engine will be shutdown and the surveillance " credit" run will be performed. The "no-credit" run will allow plant personnel to inspect the engine for fuel leaks and other abnormal conditions before performing a survellance credit run. The "no-credit" run will not significantly increase the number of starts experienced by the EDGs because of the low frequency of the maintenance that requires draining, venting, and purging the fuel oil system.
4.b. Corrective Measures Taken for the July 9, 1986 Start
! Failure:
This report will be placed in required reading for l licensed and non-licensed operators to ensure their awareness of the causes of this event. In addition, a plant modification (Engineering Design Package 1633) has been developed which will provide " Exciter Tripped" indication at the local EDG control panel. This modification will be installed during a future outage.
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Mr. James G. Keppler i August 5, 1986 NP860387 Page 7
- 5. Lenath of Time Unit Unavailable:
EDG 14 was out of service for the maintenance / surveillance activities and remained out of service until after the July 9 start failure. Therefore, unit unavailability does not apply.
- 6. Current Surveillance Test Interval:
The current surveilance test interval is once per thirty
, one days.
- 7. Verification of Conformance of Test Interval:
Because these two start failures are considered " invalid tests", as defined by Regulatory Guide 1.108, the EDG surveillance test interval is not affected. The current surveillance test interval is in conformance with Regulatory Position C.2.d of Regulatory Guide 1.108 and with Fermi-2 Technical Specification Table 4.8.1.1.2-1.
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