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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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Edison m=orthD,meHqhway - Re9. ouide 1.108 February 20, 1987 NP870106 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Reference:
Fermi 2 NRC Dochet No. 50-341 Facility Operating Licence No. NPF-43
Subject:
Emeraency Diesel Generator Start Failure Please find attached our report on one start failure of Emergency Diesel Generator (EDG) 13 which occurred on January 23, 1987. This report is submitted to you in accordance with Fermi 2 Technical Specifications 4.8.1.1.3 and 6.9.2.
If you have any questions regarding this report, please contact Mr. Lewis Bregni at (313) 586-5313.
Sincerely, l
,u Y R. S. Lenart Plant Manager ,
i cc W. G. Rogers l
J. J. Stefano USNRC Region III 00 87030203Y4 B70220 k DR ADOCK 05000341 PDR
7 U. S. Nuclear Regulatory Commission February.20, 1987 C NP870106 Page 2 ENCLOSURE 1 Emergency Diesel Generator Start Failure
- 1. Emeroency Diesel Generator ~ Involved:
Emergency Diesel Generator (EDG) 13
- 2. Identification of Failure:
Failure Date: January 23, 1987, 1319 hours0.0153 days <br />0.366 hours <br />0.00218 weeks <br />5.018795e-4 months <br /> Description of Event:
This is the second start failure of EDG 13 that occurred during what is considered an " invalid test" since the issuance of the' Fermi 2 operating license. At the time of this start f ailure there had been 109 valid test starts since the operating license was issued. The January 23, 1987 start failure is considered a failure in an " invalid test" under section C.2.e(2) of NRC Regulatory Guide 1.100 because operating error was involved in the start failure and the engine trip involved is bypassed in the emergency operating mode.
The number of start failures incurred during " valid tests" for EDG 13 since issuance of the operating license remains unchanged at zero.
- 3. Caure of Failure:
Occurrences that contributed to the cause of the start failure commenced on January 23, 1987. At 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, I&C Personnel were performing a setpoint adjustment of the EDG 13 jacket coolant pressure switch (CPS) , which is a backup to the tachometer normal speed relay (810 RPM Relay) in the starting logic. This activity caused an " engine at normal speed" signal in the start logic, although the engine was not actually started. This resulted in the receipt of a jacket coolant trouble alarm, the exciter trip alarm and the EDG 13 not ready for auto atart alarm. Since the engine was not running, there existed a low jacket coolant. water pressure, which caused the jacket coolant trouble alarm. The jacket coolant trouble also caused a non-essential engine trip nignal that sealed in.
U. S. Nuclear Regulatory Commission February 20, 1987 NP870106 Page 3 l
At 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br />, the I&C Technicians completed adjustment of-CPS and.c1 cared all alarms at the local panel by pushing the alarm reset button. Per system design,.the engine not ready ^ for autostart and the exciter trip alarms are'in the Control' Room (CR) but not at the local panel. Therefore, these alarms did not clear because the engine reset button was no't pushed. The engine reset button would have cleared the non-essential engine trip signals.
The Nuclear Supervising Operator (NSO) at the local EDG panel prepared to start the engine for the monthly start and load surveillance. The local panel alarms were all clear at thir Lime, but the engine was still tripped.
The not ready for auto start and the exciter trip alarms still existed in the CR.
The NSO at the local control panel then requested permission from the CR to start the engine.- The NSO was informed of the existence of the exciter trip alarm, however, he incorrectly reasoned that since he was going to place the exciter bypass switch in the bypass position, a reset was not necessary. The CRNSO also failed to notice the "EDG 13 not ready for auto start" alarm.
l The CRNSO then directed the NSO to start EDG 13. At
- 1319 hours0.0153 days <br />0.366 hours <br />0.00218 weeks <br />5.018795e-4 months <br />, the EDG 13 was started and tripped I approximately seven seconds later. Fuel was never admitted to the engine due to the pre-existing non-essential engine tr.ips.
[
The following errors cont-dbuted to this start failure:
l A. The Nuclear Assistant Shift Supervisor (NASS) d id not remove EDG 13 from service to perform I6C maintenance activities. Proper removal from service could have resulted in a proper return to standby service.
B. The NSO and the CRNSO failed to properly evaluate the significance of the exciter trip alarm.
The engine trip that existed during the entire sequence of events was a non-essential trip, which is bypassed if an emercency start signal is received. Hence, EDG 13 would have automatically started during an emergency, if required.
m U. S. Nuclear Regulatory Commission February 20, 1987 NP870106 Page 4-The engine tripped on the start attempt after seven seconds, per the start logic to conserve starting air.
Therefore, even after the start failure EDG 13 would have immediately started if an emergency had occurred.
Based on the above information and because the primary cause of_the start failure was operator error (not resetting the non-essential engine. trip), this is considered an " invalid test" start failure.
f.fter evaluating the cause of the start failure, the engine non-essential trip was reset, and EDG 13 was started 40 minutes after the start failure. The EDG monthly surveillance was successfully completed.
- 4. Corrective !!easures Taken1 The following corrective actions will be taken to prevent recurrence:
A. Provide required reading'for operations personnel regarding the event.
B. NASS will be counseled on philosophy of release of equipment for maintenance.
C. The !!aintenance Engineer will notify all maintenance personnel regarding the procedural requirement relative to operation of equipment by non-operations personnel.
- 5. Length of_ Time EDG Unit Unavailablet EDG 13 was available for Emergency Starts at all times during this start failure and subsequent investigation.
- 6. Current Surveillance Test Interval:
The current surveillance test interval remains unchanged at 31 days.
- 7. Ectifiqat; ion of Conformance of Tect Interval:
necause this start f ailure is considered an " invalid test" start failure as defined in Regulatory Guide 1.108 the EDG. surveillance test interval is not affected. The current surveillance test interval is in conformance with Regulatory Guide 1.108 and with Fermi 2 Technical Specification Table 4.8.1.1.2-2.