LER#78-072/03L-0 on 781003:during FNP-1-STP-40.3,the 1C Diesel Generator Output Breaker Failed to Close on 4160V Bus 1H After D/G auto-started,due to Incorrect Landing of Jumper Installed for Unit 1/Unit 2 SeparationML20064D824 |
Person / Time |
---|
Site: |
Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
---|
Issue date: |
11/02/1978 |
---|
From: |
Hairston W ALABAMA POWER CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20064D802 |
List: |
---|
References |
---|
LER-78-072-03L, LER-78-72-3L, NUDOCS 7811090200 |
Download: ML20064D824 (3) |
|
|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000348/LER-1990-0041990-07-27027 July 1990 LER 90-004-00:on 900628,determined That Procedural Inadequacy Caused Improper Surveillance of Accumulators. Sample Purge Time Too Short to Ensure Representative Sample. Procedures revised.W/900727 Ltr ML20246P8221989-07-12012 July 1989 LER 89-S02-00:on 890619,determined That Situation Existed That Could Have Allowed Unauthorized or Undetected Entry Into Svc Water Intake Structure.No Barrier Existed on Either End of Line to Prevent Access.Security Posted 05000364/LER-1984-002, Revised LER 84-002-01:on 840124,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed at Specified Times.Caused by Personnel Error.Personnel Counseled & Firewatch Patrol Immediately Performed1984-02-27027 February 1984 Revised LER 84-002-01:on 840124,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed at Specified Times.Caused by Personnel Error.Personnel Counseled & Firewatch Patrol Immediately Performed 05000364/LER-1983-054, Updated LER 83-054/03X-1:on 831028 & 1103,instrumentation Channel Associated W/Flow Transmitter FT-496 Declared Inoperable Due to Erroneous Indication.Cause unknown.FT-496 Instrumentation Channel Operable on 831029 & 11041983-12-13013 December 1983 Updated LER 83-054/03X-1:on 831028 & 1103,instrumentation Channel Associated W/Flow Transmitter FT-496 Declared Inoperable Due to Erroneous Indication.Cause unknown.FT-496 Instrumentation Channel Operable on 831029 & 1104 05000348/LER-1981-010, Updated LER 81-010/03X-1:on 810429 & 30,containment Atmosphere Radioactivity Monitoring Sys R-11 Declared Inoperable When Filter Paper Did Not Advance.Caused by Paper Spool Slipping on Shaft.Drive Shaft Adjusted1983-01-0606 January 1983 Updated LER 81-010/03X-1:on 810429 & 30,containment Atmosphere Radioactivity Monitoring Sys R-11 Declared Inoperable When Filter Paper Did Not Advance.Caused by Paper Spool Slipping on Shaft.Drive Shaft Adjusted 05000364/LER-1982-047, Corrected LER 82-047/03X-1:on 821124,determined FNP-2-STP-63.0 (Area Temp Monitoring) Not Performing Per Tech Specs.Caused by Personnel Error.Procedure FNP-2-STP-1.0 Revised.Area Temp Monitoring Completed1982-12-28028 December 1982 Corrected LER 82-047/03X-1:on 821124,determined FNP-2-STP-63.0 (Area Temp Monitoring) Not Performing Per Tech Specs.Caused by Personnel Error.Procedure FNP-2-STP-1.0 Revised.Area Temp Monitoring Completed 05000364/LER-1982-049, Corrected LER 82-049/03L-0:on 821201,containment Atmosphere Activity Monitor R-11 & R-12 Declared Inoperable When Vacuum Pump Tripped Due to Erroneous High Flow Signal. Caused by Defective High Flow Relay.Relay Replaced1982-12-23023 December 1982 Corrected LER 82-049/03L-0:on 821201,containment Atmosphere Activity Monitor R-11 & R-12 Declared Inoperable When Vacuum Pump Tripped Due to Erroneous High Flow Signal. Caused by Defective High Flow Relay.Relay Replaced 05000364/LER-1982-027, Corrected LER 82-027/03L-0:on 820622,steam Jet Air Ejector Noble Gas Activity Monitor Declared Inoperable When Pegged High While All Other Indications Normal.Caused by Faulty Detector.Detector Replaced & Declared Operable on 821982-07-12012 July 1982 Corrected LER 82-027/03L-0:on 820622,steam Jet Air Ejector Noble Gas Activity Monitor Declared Inoperable When Pegged High While All Other Indications Normal.Caused by Faulty Detector.Detector Replaced & Declared Operable on 820622 05000364/LER-1982-029, Corrected LER 82-029/03L-0:on 820623,7 River Water Pump Declared Inoperable When Motor Tripped.Caused by Ground Fault on Phase C Power Supply Cable.Defective Cable Replaced & Declared Operable on 8206261982-07-12012 July 1982 Corrected LER 82-029/03L-0:on 820623,7 River Water Pump Declared Inoperable When Motor Tripped.Caused by Ground Fault on Phase C Power Supply Cable.Defective Cable Replaced & Declared Operable on 820626 05000348/LER-1982-0311982-06-30030 June 1982 LER 82-031/03L-0:on 820531,surveillance Requirement for Radiation Monitor R-60A Not Performed Per Tech Specs.Caused by Personnel Error.Surveillance Performed.Personnel Instructed 05000348/LER-1982-0241982-06-30030 June 1982 LER 82-024/03L-0:on 820601,containment Atmosphere Activity Monitors R-11 & R-12 Declared Inoperable When Inboard & Outboard Pumps Tripped Due to Erroneous Low Flow Signal. Caused by Setpoint Drift.Setpoints Adjusted 05000348/LER-1982-0291982-06-30030 June 1982 LER 82-029/03L-0:on 820605,containment Airlock Declared Inoperable When Airlock Outer Door Could Not Be Shut.Caused by Broken Door Shaft.Shaft Repaired 05000348/LER-1982-0281982-06-30030 June 1982 LER 82-028/03L-0:on 820605,during Performance of FNP-1-STP-22.16,turbine Driven Auxiliary Feedwater Pump Failed to Start.Caused by Faulty Limit Switch on Valve HV-3226.Limit Switch Replaced 05000348/LER-1982-0231982-06-25025 June 1982 LER 82-023/03L-0:on 820528,determined That FNP-2-STP-19.3 Not Performed within Time Interval Specified by Tech Spec 4.0.5.Caused by Personnel error.FNP-2-STP-19.3 Satisfactorily Performed 05000348/LER-1982-0271982-06-25025 June 1982 LER 82-027/03L-0:on 820526,turbine Driven Auxiliary Feedwater Pump Declared Inoperable When Main Control Board Annunciator Indicated Trip Throttle Valve Closed.Cause Unknown.Valve Reopened 05000348/LER-1982-0251982-06-11011 June 1982 LER 82-025/03L-0:on 820519, a Train Chlorine Detector Declared Inoperable When Alarm Sounded & Would Not Reset. Caused by Faulty Photocell Light Bulbs.Bulbs Replaced & Detector Returned to Svc 05000348/LER-1982-0221982-06-11011 June 1982 LER 82-022/03L-0:on 820519,during Performance of FNP-2-STP-4.7,charging Pump 2A Would Not Start.Caused by Failure of Breaker DF06 to Close Due to Misaligned Microswitch Arm.Arm Repaired 05000348/LER-1982-0191982-06-0202 June 1982 LER 82-019/03L-0:on 820508,exhaust Fan Failed to Start, Rendering B Train Penetration Room Filtration Sys Inoperable.Caused by Worn Fan Belts Which Slipped Off Pulleys.Belts Replaced 05000348/LER-1982-0201982-06-0202 June 1982 LER 82-020/03L-0:on 820504,snubber 2MS-R-530 Declared Inoperable Since Reservoir Devoid of Fluid.Caused by Fluid Leak on Improperly Installed O Rings.O Rings Replaced & Snubber Declared Operable 05000364/LER-1982-0191982-05-27027 May 1982 LER 82-019/03L-0:on 820430,pressurizer Pressure Fell Below Tech Spec Limit.Caused by Transient in Pressurizer Pressure Transmitter PT-444 Opening Spray Valve.Pressure Restored 05000364/LER-1982-0171982-05-27027 May 1982 LER 82-017/03L-0:on 820427,during Full Length Control Rod Operability test,FNP-2-STP-5.0 Group 1 & Control Banks a, Group 1 & B,Group 1 Control Rods Declared Inoperable.Caused by Faulty Slave Cycler Counter Card.Card Replaced 05000348/LER-1982-0121982-04-0202 April 1982 LER 82-012/03L-0:on 820318,boron Injection Tank Train a Heat Tracing Inoperable Due to Failure of Two Circuits in Train. Caused by Electronic Failure Due to Heat Buildup in Electronic Cabinets.Controller Cards Replaced 05000348/LER-1982-0111982-04-0202 April 1982 LER 82-011/03L-0:on 820316,120-volt Ac Vital Bus B de-energized When Inverter 2B Tripped.Caused by Failed Inverter 2B Due to Blown Fuse in Voltage Regulator Circuit. Fuse Replaced 05000348/LER-1982-0101982-04-0202 April 1982 LER 82-010/03L-0:on 820304,during RCS Leakage Test, Unidentified RCS Leak Rate Exceeded Tech Spec Limit.Caused by Packing Leak from Flow Control Valve FCV 122.Packing Adjusted 05000348/LER-1982-0091982-04-0202 April 1982 LER 82-009/03L-0:on 820312,instrumentation Loop Associated W/Pressurizer Pressure Transmitter PT-455 Declared Inoperable When Transmitter Failed Low.Caused by Faulty Power Supply Card.Card Replaced 05000348/LER-1982-0081982-04-0202 April 1982 LER 82-008/03L-0:on 820307,instrumentation Loop Associated W/Steam Flow Transmitter FT-476 Declared Inoperable When Transmitter Failed Low.Caused by Faulty Power Supply Card. Card Replaced & Calibr 05000348/LER-1982-0071982-04-0202 April 1982 LER 82-007/03L-0:on 820305,remote Shutdown Panel Pressurizer Level Indicator LI-459Z Declared Inoperable When Failed High.Caused by Faulty Transmitter Amplifier Board.Board Replaced & Transmitter Calibr ML20064H8871978-12-22022 December 1978 /03L-0 on 781125:Train a River Water Pumps Were Found in Tripped Condition & Could Not Be Started from Control Room.Cause of Occurrence Is Undetermined ML20064H9331978-12-21021 December 1978 /03L-0 on 781221:vibration Readings Taken on River Water Pump 4 Exceeded Acceptable Limits.Work on Pump Bedplate,Adjustment of Impeller Lift & Pump/Motor Realignment Restored Vibration to W/In Acceptable Range ML20064H9191978-12-21021 December 1978 /03L-0 on 781221:both Trains of Component Cooling Water Were Discovered to Be cross-connected at Charging Pump 1B.FNP-1-STP-23.7 Was Rev to Show Alignment of Charging Pump 1B to Either Train ML20064H9281978-12-20020 December 1978 /03L-0 on 781120:train a River Water(Rw)Pump 9 Secured Due to Vibration.Tech Specs Req at Least 2 Independent RW Loops to Be Operable.Caused by Bearing Damage Due to Fouling of Lube/Cooling Piping ML20064H4111978-12-15015 December 1978 /03L-0 on 781114:both Containment Atmosphere Particulate (R-11) & Gaseous (R-12) Radioactivity Monitoring Sys Were Declared Inoperable After Vacuum Pump Tripped & Would Not Restart,Due to Broken Wire in low-flow Relay ML20064G3771978-12-0404 December 1978 /03L-0 on 781102:noted That FNP-1-STP-41.2 Specified IR Neutron Flux High Level Trip Setpoint Limits Were Less Conservative than Tech Spec Limits.Caused by Failure to Revise FNP-1-STP-41.2 to Reflect New Setpoint ML20064F6111978-11-27027 November 1978 /01T-0 on 781114:water Levels in Fire Protec Sys Water Storage Tanks Were Approx 135,000 Gallons Less than Prescribed Minimum,Due to Constr Personnel Diverting Water to Unit 2 Condenser for Hydrostatic Test ML20064F1251978-11-22022 November 1978 /03L-0 on 781025:B Train Penetration Room Filtration Sys Inoperable.Caused by Low Spring Tension on Filter Support Assembly ML20064F2791978-11-20020 November 1978 /03X-1 on 780527:during Unit Startup,B S/G Code Safety Valve Lifted Causing Tavg to Drop Below 541 Degrees F in Violaion of T/S3.1.1.5.Caused by Broken Lower Adjusting Ring Locking Pin.Valve Was Replaced ML20064F2741978-11-20020 November 1978 /03L-0 on 781102:during Surveillance Test FNP-0- STP-15.0,exterior Door Seals Were Leaking.Caused by Dirty Air Lock Exterior Door Seals.Seals Cleaned & Retested Satisfactorily ML20064F2711978-11-20020 November 1978 /03L-0 on 781027:while in Mode 1,the Steam Line Pressure Instru Assoc W/Pressure Transmitter PT-484 Failed Low.Caused by Failure of Loop Pwr Supply isolated/non- Isolated(Nlp)Card POY-484 ML20064E7251978-11-13013 November 1978 /03L-0 on 781016:the a Train Undervoltage Relay 27-1 on RCP 1A Failed to Trip at Required Setpoint During Test Procedure FNP-1-612.0 Due to Setpoint Drift ML20064D8241978-11-0202 November 1978 /03L-0 on 781003:during FNP-1-STP-40.3,the 1C Diesel Generator Output Breaker Failed to Close on 4160V Bus 1H After D/G auto-started,due to Incorrect Landing of Jumper Installed for Unit 1/Unit 2 Separation ML20064D8171978-11-0202 November 1978 /03L-0 on 781003:train a River Water Pumps Found in Tripped Condition & Could Not Be Started from Control Room,Caused by Low Level Reed Switch Failure in Pond Level Switch LS511 ML20064D8091978-11-0202 November 1978 /03X-1 on 780914:inspec of Diesel Generator Bldg Noted Lb D/G Air Start Sys Air Reservoir 1A,1B Pressures Were 210 PSIG & 80 Psig,Due to 1B Air Compressor Relief Valve/Check Valve Leakage ML20064D8051978-11-0202 November 1978 /03X-1 on 780909:during Surveillance Test FNP-1- STP-22.0,the Turbine Driven Auxiliary Feedwater Pump Failed to Start When Trip/Throttle Valve Tripped Shut & Control Was Lost on Valves 3228A,B,C,due to Failed Tdafpcircuit Relay ML20147B3631978-10-0202 October 1978 /01T-0 on 780922:during Inspec of Class I & II Pipe Restraints/Snubbers,Noted That Main Feedwater Line Lateral Seismic Restraint FW-R49 Was Not in Place.Reason or Date of Removal Not Determined;Unit Reinstalled ML20147B3181978-10-0202 October 1978 /03L-0 on 780905:failure of 1-2A Diesel Generator to Respond to Voltage/Speed Control in Auto Due to Failure of Motorized Potentiometer(Failed Diodes)Causing the 125V DC Supply Fuses to Blow 1990-07-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
[Table view] |
Text
.
4RC FORM 366 U. S. R5UCLEAR REGULATORY COMMISSION (7 771 LICENSEE EVENT REPORT CONTROL BLOCK: l 6
l l l l l lh 6
LPLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) bei@
l Loli.]8 9I AI tiLICENSEE 7
al niCODE rl 11@l OI 14 IS 01 -I el 01 O! 0101 -I 01 Ol@l LICENSE NUMBER 2$
411 26 11 11 11 l@l$7 CAT LICE
- SE T YPE JG CON'T lolil [',%lLj@l0l 5l0l0lOl314l81@[1 10 68 69 10 13 17 18 l@l1111Ol2l7I8l@
E% ENT DATE 74 75 REPORT DATE 80 7 8 60 61 DOCK ET Nuve ER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Lo.MJ l on 10/3/78, while performing FNP-1-STP-40.3 (partial) the 1C diesel generator (D/G) l I o l 31 l output breaker failed to close on 4160V bus 1H after the D/G auto-started and came upl
[ o 1. l l to speed. The 1C D/G was declared inoperable at 1015 on 10/3/78, and was returned tol
[olsl l an operable status at 1110 on 10/3/78. T/S 3.8.1.2 requirements were met (one l 1010l l separate independent D/G set operable). The 1C D/G output breaker could have been l o 7 l closed and the D/C loaded manually. The health and safety of the public were not l IoI8Il affected. 80 I
7 89 Coc'Eo" '#C0"o*E S sC0DE COMPONENT CODE SUSC DE 5 C E y
7 8 lE lE l@ yh l Zlh lZ lZ lZ lZ lZ lZ lh Jh J h 9 10 11 12 13 18 19 20 SE QUE NTI AL OCCURRENCE REPORT REVISION
,,, EVENT YE AR REPORT NO. CODE TYPE NO.
f
@ y"tER'Ro ugRT
_ 21 l7l8l 22
[.--j 23 l0l7l2l 24 26 y
27 l Ol 3l 28 29 W
30
[-.]
31 J
32 N ACT oN oN PL NT MET HOURS 22 SB IT FORAf b 8. SUPPLI MAN FACTURER W
33
@l.31@
34 LZ 36 - l@
L.Z 36 1@ l0IoIoIoI 37 40 I41Y l@ lN lg 42 yg 43 l44 Z l9 l9 l947l@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l1Io11 A jumper installed for Unit 1/ Unit 2 separation was incorrectly landed. The jumper l i i l was correctly positioned and the operability of the IC D/C verified per FNP-1-STP-40.31 1
Iil2l 1 (partial). A review of documentation verified the jumper was initially positioned l q l correctly. This occurrence will be discussed with applicable plant personnel. l 1
I 11 1411 80 7 8 9 ST % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION y ]@ l 0 l 0 l 0lgl NA l W gl Surveillance Testing l ACTIVITY CONTENT REuASEo op aEtt ASE to27,0N o, REttASE @
NA -OuN10, ACTIVITY @l l NA l li is8 I9 U @ W@l 7 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE CESCRIPTION I
t i l 71 1 01 01 Ol@lZ l@l sA PE RSON~El'imu'2 ES NuveER oESCRiPTiON@
NA l li la 8l 9l 0l 0l 0l@l 7 11 12 80 TvPE CESC PT ON l1l91IZlh] NA l
781109C X O NRc OSE O~ty L2J 9.J L21 iSsuf lDoESCRiPTiOn NA g l lllllllllllllj 7 8 9 10 68 69 B0 &
NAVE OF PREP ARER W. G. Hairston, III PHONE:
O $
O ALABAMA P0b'ER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET No. 50-348 ATTACHMENT TO LER 78-072/03L-0 Facility Joseph !!. Farley Unit 1 ,.
Report Date: 11/02/78 I ".
Event Date: 10/03/78 >-.
9..
. Identification of Event Diesel generator 1C output breaker failed to close on 4160V bus 1H during performance of Surveillance Test Procedure FNP-1-STP-40.3.
Conditions Prior to Event
' The unit was in Mode 5 during a scheduled unit shutdos..
Description of Event On 9/18/78, while performing FNP-1-STP-40.3 to determine the operability of the on-site emergency power system during a safety injection in
'7 conjunction with a loss of off-site power, the 1C diesel generator started and came up to speed in the required time, but did not close on 4160V bus 1H. The reactor operator increased the 1C diesel generator voltage, which was low, and manually closed the 1C diesel generator out-put breaker. It was thought that the failure of the 1C diesel generator output breaker to close was related to the low voltage, and that the operability of the diesel generator was not affected.
A retest of FNP-1-STP-40.3 (partial) was performed on 10/3/78 to verify the ability of the 1C diesel generator to auto-start and pick up the required loads. When bus lH was deenergized, the 1C diesel generator I auto-started, came up to the required speed and voltage, but the output f breaker did not close on the lH bus. The 1C diesel generator was
- declared inoperable at 1015, and a work request was initiated to investi-gate and correct the problem.
' A jumper, initially installed for Unit 1/ Unit 2 separation during the startup test program prior to initial core load was found to be improperly landed. The jumper was correctly positioned and FNP-1-STP-40.3 (partial) was completed satisfactorily for the 1C diesel generator. The 1C diesel generator was returned to an operable status at 1110 on 10/3/73.
Designation of Apparent Cause A jumper installed for Unit 1/ Unit 2 separation was incorrectly landed.
j A review of plant documentation indicated that the jumper was installed correctly when the Temporary Alterations Log was implemented prior to initial core load. The 1C diesel generator auto-started and loaded as required when a loss of off-site power occurred on 9/16/78 (LER 77-012/01T-1).
The 1C diesel generator was also verified to be operable by the loss of off-site power test performed as part of the Phase III test program on e 4 .s m 24 s . . s **.P l
78-072/03L-0 10/2/77 and 10/3/77. A review of maintenance work requests revealed no evidence of the jumper being moved since its initial installation.
No cause could be deternined for the incorrect placement of the jumper.
Analysis of Event The 1C diesel generator could be aligned manually. The loads supplied (river water pumps 8, 9, and 10) would not be required in the early stages of an accident, therefore, operations personnel would have adequate time to close the breaker and manually load the diesel genera-tor. The other redundant diesel generator set was operable. At the time of discovery only one diesel generator set was required to be operable (unit in Mode 5). The health and safety of the general public were not affected by this occurrence.
Effect of Plant This occurrence had no significant effect on plant operation.
Corrective Action The jumper was correctly positioned af ter being discovered incorrectly positioned. The operability of the 1C diesel generator was verified by FSP-1-STP-40.3 (partial) . This incident will be discussed with applicable plant personnel.
Failure Data None.
l l
_ _