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| l l l l 6 | | l l l l 6 |
| lh (PLE ASE PRINT OR T'. ELL RECUIRED INFORMATION) l 01 Hj Dl Bl Sl 1l@l0 l0 l- l0 l0 lN lP IF l IO l1-25l@!264 I 1UCENSE l 1 !TYPE 1 l JG1 lh!_ l SSl@ | | lh (PLE ASE PRINT OR T'. ELL RECUIRED INFORMATION) l 01 Hj Dl Bl Sl 1l@l0 l0 l- l0 l0 lN lP IF l IO l1-25l@!264 I 1UCENSE l 1 !TYPE 1 l JG1 lh!_ l SSl@ |
| 57 .;AT 7 3 LICENSEE CCDE 14 15 LICENSE NuMS ER CO | | 57 .;AT 7 3 LICENSEE CCDE 14 15 LICENSE NuMS ER CO lol11. ERCI I L l@l 0 15 10 l- 10 13 14 16 @ l0 16 [0 14 17 i8 l@l0l612181 64 63 EV ENT D ATg 74 75 REPORT QATE 80 I 8 60 61 COCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 21 l On '6/4/78 while perforr.ing surveillance testing, Diesel Generator (DG) 1-1 failed to l |
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| lol11. ERCI I L l@l 0 15 10 l- 10 13 14 16 @ l0 16 [0 14 17 i8 l@l0l612181 64 63 EV ENT D ATg 74 75 REPORT QATE 80 I 8 60 61 COCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 21 l On '6/4/78 while perforr.ing surveillance testing, Diesel Generator (DG) 1-1 failed to l | |
| [o !al l Operate with proper frequency and voltage. The test was suspended and DG l-1 declaredl Io Ie 1 l inoperable. The unit was in Mode 6 at the ti=c of the occurrence. This incident is l Io isi I being reported as a component failure. There was no danger to the health and safety [ | | [o !al l Operate with proper frequency and voltage. The test was suspended and DG l-1 declaredl Io Ie 1 l inoperable. The unit was in Mode 6 at the ti=c of the occurrence. This incident is l Io isi I being reported as a component failure. There was no danger to the health and safety [ |
| i l o 16 j l of the public or unit personnel. Diesel Generator 1-2 was operable had e=ergency (NP-33-78-74) l I O l 7 l l power been required. | | i l o 16 j l of the public or unit personnel. Diesel Generator 1-2 was operable had e=ergency (NP-33-78-74) l I O l 7 l l power been required. |
| I l o l e I 'l __ 80 CAUSE COMP. VALVE SYSTEM CAUSE CCOE SU8 CODE COMPONENT CODE SUSCCOE SUSCODE CODE lo191 lE l3 j @ lE l@ l A l@ lG lE IN lE IR l A lh lD lh l Zlh 12 18 19 20 7 8 9 10 ft 12 4EVISION SEOUENTI AL OCCURRENCE REPORT | | I l o l e I 'l __ 80 CAUSE COMP. VALVE SYSTEM CAUSE CCOE SU8 CODE COMPONENT CODE SUSCCOE SUSCODE CODE lo191 lE l3 j @ lE l@ l A l@ lG lE IN lE IR l A lh lD lh l Zlh 12 18 19 20 7 8 9 10 ft 12 4EVISION SEOUENTI AL OCCURRENCE REPORT REPORT NO. CODE TYPE NC. |
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| REPORT NO. CODE TYPE NC. | |
| EVENT YEAR | | EVENT YEAR |
| * O arg;s LE RtRO 17181 | | * O arg;s LE RtRO 17181 |
| ,_ 21 22 1-1 23 10 !6 l2 I 24 26 W27 I 01 31 23 29 W | | ,_ 21 22 1-1 23 10 !6 l2 I 24 26 W27 I 01 31 23 29 W |
| 30 1-l 31 I 0l 32 | | 30 1-l 31 I 0l 32 ME M HOURS 22 5 8 i C FOR 8. SUPPLi$ MANUFAC RER EN 'ACT ON CN PLANT |
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| ME M HOURS 22 5 8 i C FOR 8. SUPPLi$ MANUFAC RER EN 'ACT ON CN PLANT | |
| ,)lAj@lZj@ l Z [g l36Z lg 3l10 l0 l0 l- 40 l lY lg 41 lY lg 42 l43A l@ lP l3 l1 [8 l] | | ,)lAj@lZj@ l Z [g l36Z lg 3l10 l0 l0 l- 40 l lY lg 41 lY lg 42 l43A l@ lP l3 l1 [8 l] |
| 64 47 33 34 35 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS f | | 64 47 33 34 35 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS f |
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| }1 l6l 7 8 9 l Zl@ lZ 10 11 A4 45 80 PERSONNEL EXPCSURES | | }1 l6l 7 8 9 l Zl@ lZ 10 11 A4 45 80 PERSONNEL EXPCSURES |
| * NuveER TV8E DESCRIPTION 39 | | * NuveER TV8E DESCRIPTION 39 |
| _ a g t,i l l1 l7ll0l0l0 lZ A | | _ a g t,i l l1 l7ll0l0l0 lZ A PERSONNE L INJURIES Q Ag ge.,i p NUv9ER DESCRIPTION l |
| * PERSONNE L INJURIES Q Ag ge.,i p
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| NUv9ER DESCRIPTION l | |
| ii n i 10 ! Q i O t1l@l 12NA (\*,,.[ s: | | ii n i 10 ! Q i O t1l@l 12NA (\*,,.[ s: |
| 7 (' % 9 | | 7 (' % 9 |
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| .___ -- . _ - - .- - .- - . - . - . _ . - - _ . . - .__.=. _... ._ . | | .___ -- . _ - - .- - .- - . - . - . _ . - - _ . . - .__.=. _... ._ . |
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| .. - z. . | | .. - z. . |
| G., | | G., |
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| = | | = |
| TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION | | TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER UP-33-78-74 l DATE OF EVENT: June 4, 1978 FACILITY: Davis-Besse Unit 1 , |
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| SUPPLEMENTAL INFORMATION FOR LER UP-33-78-74 | |
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| l DATE OF EVENT: June 4, 1978 FACILITY: Davis-Besse Unit 1 , | |
| f | | f |
| ; IDENTIFICATION OF OCCURRENCE: Diesel Generator 1-1 declared inoperable on June 4, 1978. | | ; IDENTIFICATION OF OCCURRENCE: Diesel Generator 1-1 declared inoperable on June 4, 1978. |
| l | | l l Conditions Prior to Occurrence: The unit was in Mode 6., with Power (5"I) = 0 and Load (M4E) = 0, a |
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| l Conditions Prior to Occurrence: The unit was in Mode 6., with Power (5"I) = 0 and Load (M4E) = 0, a | |
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| Description of Occurrence: At 0545 hours on June 4,1978, while performing Surveil-l | | Description of Occurrence: At 0545 hours on June 4,1978, while performing Surveil-l |
| ; lance Test ST 5031.07, " Safety Features Actuation System (SFAS) 18 Month or Refuel-ing Test" Diesel Generator 1-1 came up to speed but the generator breaker did not j | | ; lance Test ST 5031.07, " Safety Features Actuation System (SFAS) 18 Month or Refuel-ing Test" Diesel Generator 1-1 came up to speed but the generator breaker did not j |
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Line 68: |
| ; " Diesel Generator Monthly Test", was performed. Upon starting Diesel Generator 1-1, l l the frequency was' not stable and the generator voltage was icw. The test was sus- , | | ; " Diesel Generator Monthly Test", was performed. Upon starting Diesel Generator 1-1, l l the frequency was' not stable and the generator voltage was icw. The test was sus- , |
| pended at this point, and the diesel generator declared inoperable. | | pended at this point, and the diesel generator declared inoperable. |
| This occurrence did not place the unit in the Action Statement: of Technical Speci- | | This occurrence did not place the unit in the Action Statement: of Technical Speci-fication 3.8.1.2 because the unit was in Mode 6, which requires only one diesel generator to be operable while in Modes 5 or 6. This incident is being reported as a component failyss. |
| .,
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| fication 3.8.1.2 because the unit was in Mode 6, which requires only one diesel generator to be operable while in Modes 5 or 6. This incident is being reported as a component failyss. | |
| Designation of Aeoarent Cause of Occurrence: The cause of this occurrence can be i attributed to a component failure of a primary potential fuse for the diesel generator. | | Designation of Aeoarent Cause of Occurrence: The cause of this occurrence can be i attributed to a component failure of a primary potential fuse for the diesel generator. |
| Analysis of Occurrence: . There was no danger to the health and safety of the public or to unit personnel. Diesel Generator 1-1 was not required for emergency power during the period of time it was inoperable.- Diesel Generator 1-2 was operable | | Analysis of Occurrence: . There was no danger to the health and safety of the public or to unit personnel. Diesel Generator 1-1 was not required for emergency power during the period of time it was inoperable.- Diesel Generator 1-2 was operable |
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Line 74: |
| had emergency power been required. , | | had emergency power been required. , |
| j Corrective Action: Under Maintenance Work Order 78-1332, the primary potential fuse for Diesel Generator 1-1 wcs replaced. | | j Corrective Action: Under Maintenance Work Order 78-1332, the primary potential fuse for Diesel Generator 1-1 wcs replaced. |
| 4 | | 4 At 1515 hours on June 4,1978, Surveillance Test ST 5081.01, Diesel Generator Monthly Test, was completed and the diesel generator declared operable. |
| * At 1515 hours on June 4,1978, Surveillance Test ST 5081.01, Diesel Generator Monthly Test, was completed and the diesel generator declared operable.
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| 1 , | | 1 , |
| Fa i lure Data: No previous si=ilar events have occurred. | | Fa i lure Data: No previous si=ilar events have occurred. |
| 4 LER #78-062 | | 4 LER #78-062 |
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| ,,..-___,,_,,...-..y,.. , _ _ _ . , . m.___. , , , - . .,- ,,_,.,_,,._,,.,_._,,m.m_m,. ,_..,.,,,.,,,,..,#-.- - - . _ , . _ ..,.,m-}} | | ,,..-___,,_,,...-..y,.. , _ _ _ . , . m.___. , , , - . .,- ,,_,.,_,,._,,.,_._,,m.m_m,. ,_..,.,,,.,,,,..,#-.- - - . _ , . _ ..,.,m-}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046C0661993-07-30030 July 1993
LER 92-009-01:on 920910,deficiencies Discovered During Dynamic Testing of Motor Operated Valves in Response to Generic Ltr 89-10.MOVs W/Deficiencies Modified or Repaired. W/930730 Ltr
ML20046B6011993-07-26026 July 1993
LER 93-004-00:on 930428,plant Entered Mode 2 W/Afw Pump Turbine Main Steam Line Crossover Check Valve MS735 in Open Position.Caused by Inappropriate Use of Engineering Judgement.Valve MS735 closed.W/930726 Ltr
ML20045D2451993-06-17017 June 1993
LER 93-003-00:on 930520,plant Experienced Trip from Approx & Continuity Between Fuse & Fuseholder Lost,Resulting in Loss of Selected RCS Average Temp Input to Ics.Faulty Fuse Cap & Fuse replaced.W/930617 Ltr
ML20044B1681990-07-10010 July 1990
LER 90-002-01:on 900126,reactor Coolant Pump Current Monitor Inputs to Sfrcs ACH1 & Reactor Pressure Sys Channel 1 Experienced Reactor Trip.Probably Caused by Inadequate Test Switches & Isolation plug.W/900710 Ltr
ML20043H3201990-06-18018 June 1990
LER 90-010-00:on 900518,station Experienced Inadvertent Safety Features Actuation Signal Level 1-4 Actuation W/Injection of 1,000 Gallons of Borated Water.Caused by Loss of 120-volt Ac Bus Y3.W/900618 Ltr
ML20043B5711990-05-25025 May 1990
LER 90-008-00:on 900425,safety Features Actuation Sys Level 1 Actuation Occurred,Resulting in Trip of Containment Radiation Monitors.Caused by High Radiation Fields While Lifting Core Support Assembly.Mod initiated.W/900525 Ltr
ML20043B8051990-05-25025 May 1990
LER 90-009-00:on 900426,source-check of Station Vent Radiation Monitors Not Performed Per Tech Spec 3.3.3.10. Caused by Use of Outmoded Light Emitting Dioide as Check Source.Source Check Procedures revised.W/900525 Ltr
ML20042F2811990-05-0303 May 1990
LER 90-007-00:on 900403,inadvertent,inconsequential Safety Features Actuation Signal Occured While Defueled.Caused by Incidental Contact W/Monitor in Containment.Temporary Barriers Built Around monitors.W/900503 Ltr
ML20042F2791990-05-0303 May 1990
LER 90-006-00:on 900403,station Experienced Safety Features Actuation Sys Levels 1 Through 5 Actuation.Caused by Contact W/Breaker Switch HAAE2 in High Voltage Switchgear Room 2. Meetings Held W/Craft personnel.W/900503 Ltr
ML20042E4891990-04-16016 April 1990
LER 90-005-00:on 900314,determined That Some Class 1E Circuits That Pass Through Containment Electrical Penetrations Do Not Have Adequate Backup Fault Protection. Caused by Inadequate Design control.W/900416 Ltr
ML20012D0341990-03-19019 March 1990
LER 90-004-00:on 900217,fuel Assembly Moved in Spent Fuel Pool While Emergency Ventilation Inoperable.Caused by Personnel Error.Personnel Involved Counseled & Subj LER Part of Required reading.W/900319 Ltr
ML20012C7151990-03-14014 March 1990
LER 90-003-00:on 900212,station Entered Mode 6,refueling,w/o Operable Audible Source Range Indication.Caused by Personnel Error.Individual counseled.W/900314 Ltr
ML20012B4851990-03-0606 March 1990
LER 83-039/03X-2:on 830726,discovered That Handwheel for Inner Door of Personnel Airlock in Shut Position & Partially Opened.Caused by Excessive Use of Door During Outages.Door Repaired & Returned to Operable status.W/900306 Ltr
ML20011F3831990-02-26026 February 1990
LER 90-002-00:on 900126,reactor Tripped from 73% Power. Caused by Spurious Reactor Coolant Pump Monitor Signal Indicating Only One Pump Running in Each Loop.Pump Seal to Be Replaced During Sixth Refueling outage.W/900226 Ltr
ML20006E6861990-02-20020 February 1990
LER 90-001-00:on 900118,reactor Protection Sys Channel 2 Bypassed Temporarily During Performance of DB-MI-03207. Caused by Inadequate Procedure Re Inoperable Channel Removal.Procedure SP1105.02 revised.W/900220 Ltr
ML20011E2251990-01-30030 January 1990
LER 86-032-01:on 860802,inadvertent Start of High Pressure Injection Pump 1-2 Occurred.Caused by Open Relay Coil. Failed Relay Replaced & Procedure Change Initiated. W/900130 Ltr
ML20005G1091990-01-0909 January 1990
LER 89-015-01:on 891026,concluded That Transmitter Was Out of Tolerance When Reactor Protection Sys Channel 2 Returned to Operable Status on 890924.Caused by leak-by in Instrument Manifold.Transmitter Recalibr successfully.W/900109 Ltr
ML20042D4011990-01-0202 January 1990
LER 89-010-01:on 890612,control Room Ventilation Sys Declared Inoperable Due to Compressor High Pressure Trips. Caused by Tripping of Refrigerant Pressure Switch on High Pressure.Switch Reset & Sys retested.W/900102 Ltr
ML19354D7361989-12-22022 December 1989
LER 89-018-00:on 891123,hydrogen Dilution Blower 1-1 Casing Drain Line Broke Off at Casing,Declaring Blower Inoperable. Caused by Drain Line Being Accidentally Stepped On.Drain Removed & Pipe Plug installed.W/891222 Ltr
ML19332F8951989-12-13013 December 1989
LER 89-017-00:on 891113,containment Spray Pump 1-1 Inadvertently Started During Monthly Functional Test in Safety Features Actuation Sys (Sfas) Channel 1.Caused by Failed Relay in Sfas Channel 3.Relay replaced.W/891213 Ltr
ML19332E7521989-12-0404 December 1989
LER 89-016-00:on 890917,unplanned Release of Radioactive Resin to Onsite Settling Basin Occurred.Caused by Personnel Error.Standing Order 89-051 Generated on 890920 to Direct Use of Working Copy of procedures.W/891204 Ltr
ML19332D3111989-11-27027 November 1989
LER 89-015-00:on 890924,RCS Flow Transmitter Out of Tolerance When Reactor Protection Sys Channel 2 Returned to Operable Status.Caused by leak-by in Instrument Manifold Seen as Zero Shift.Transmitter recalibr.W/891127 Ltr
ML19324C2081989-11-10010 November 1989
LER 89-014-00:on 891011,plastic Sheeting Blocked Off Fire Detectors in Auxiliary Feedwater Pump 1-1 Room & High Voltage Switchgear Room B,Making Fire Detectors Inoperable. Caused by Personnel Oversight.Event reviewed.W/891110 Ltr
ML19325D4671989-10-16016 October 1989
LER 89-004-01:on 890411,determined That Circulating Water Line Break Would Result in Loss of Svc Water as Result of Concerns Raised on 890206.Cause Unknown.Standing Order 89-026 in Place to Plug Floor drains.W/891016 Ltr
ML19325C8531989-10-13013 October 1989
LER 89-013-00:on 890913,hourly Fire Watch Patrol Exceeded Allowed Interval,Violating Tech Spec 3.7.10,Action a.2. Caused by Personnel Error.Individual Counseled & Event Info Distributed to Fire Watch personnel.W/891013 Ltr
ML20024E2591983-08-0101 August 1983
LER 83-033/03L-0:on 830620,fire Detection Zone Reactor Coolant Pump 1-2,containment Level 603 Ft Alarmed & Could Not Be Reset.Caused by Faulty Detector String.Zone Will Be Restored During Next Refueling outage.W/830801 Ltr
ML20024B8351983-07-0101 July 1983
LER 83-028/03L-0:on 830603 & 17,fuel Handling Area Radiation Monitors RE8446 & 7 Found Deenergized.Caused by Blown Radiation Monitoring Cabinet Fuse.Fuse replaced.W/830701 Ltr
ML20024B0471983-06-21021 June 1983
LER 83-026/03L-0:on 830524,one Half Channel Trip in Steam & Feedwater Rupture Control Sys (Sfrcs) Channel 2 Received. Caused by Component Failure.Input Buffer replaced.W/830621 Ltr
ML20024A3621983-06-0909 June 1983
LER 83-024/03L-0:on 830511,while Starting Up from 830510 Reactor Trip,Quadrant Power Tilt in Quadrant Yz Exceeded Tech Spec steady-state Limit.Caused by Inherent Design of B&W NSSS & Negative Moderator Temp coefficient.W/830609 Ltr
ML20024A5341983-06-0808 June 1983
LER 83-023/03L-0:on 830510,120-volt Ac Essential Bus Y4 Lost,Resulting in Deenergizing Reactor Protection & Safety Features Actuation Sys Channel 4.Caused by Blown Fuse in Inverter YV4.Power Restored to bus.W/830608 Ltr
ML20024A5481983-06-0707 June 1983
Revised LER 83-002/03X-2:on 830115,18,0409,10 & 0510,RCS Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Slight Fission Product Leakage Through Fuel Cladding.Level of I-131 monitored.W/830607 Ltr
ML20023D9051983-05-26026 May 1983
LER 83-027/03L-0:on 830428,valve RC240B Would Not Close W/O Repeated Signals from Control Room.Caused by Valve Operator Torquing Out Due to Dirty & Improperly Lubricated Stem.Stem Cleaned & Torque Switch reset.W/830526 Ltr
ML20023C3241983-05-0505 May 1983
LER 83-016/03L-0:on 830407,determined That Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed.Caused by Component Failure within Amplifier. Amplifier Replaced
ML20023C3021983-05-0505 May 1983
Revised LER 83-002/03X-1:on 830115,RCS Dose Equivalent I-131 Exceeded Tech Spec Limit of 1.0 Uci/Gm.Caused by Leakage of Fission Products Through Fuel cladding.I-131 Monitored Until Level Dropped
ML20028E9581983-01-19019 January 1983
LER 82-068/03L-0:on 821220,core Imbalance Vs Core Power Limit Computer Alarm C963 Inoperable.Caused by Mistake in Alarm Subroutine.Alarm Statement Corrected So Limits & Value for Imbalance Scaled Same
ML20028D2291983-01-0707 January 1983
Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint
ML20028C1231983-01-0303 January 1983
LER 82-064/03L-0:on 821129,decay Heat Cooler Component Cooling Water Outlet Valve on CCW Train 1 Would Not Open. Caused by Mfg Error.Flanged Bearing Missing from Actuator Mounting Plate.Flanged Bearing Installed on 821215
ML20028C3111982-12-30030 December 1982
Revised LER 81-031/03X-6:on 810512,following Reactor Trip, RCS Sample Level Peaked Above Microcurie Limit.Other Iodine Spikes Occurred 810730,0902,1016 & 23 & 1228.Caused by Slight Leakage of Fission Products Through Fuel Cladding
ML20028C1971982-12-30030 December 1982
Revised LER 82-045/03X-1:on 820904 & 1203,auxiliary Feedwater Pump 1-1 Suction Valve FW786 Closed for No Apparent Reason W/O Operator Touching Close Button.Cause Unknown.Valve FW786 Reopened Upon Discovery
ML20028C2591982-12-30030 December 1982
LER 82-065/03L-0:on 821201,discovered That Control Room Not Placed in Recirculation Mode within 1 H of Ventilation Sys Chlorine Detector Being Taken Out of Svc.On 821203,chlorine Detector Failed.Caused by Personnel Error
ML20028B0291982-11-19019 November 1982
LER 82-054/03L-0:on 821021,Door 107 to Radiation Equipment Found Partially Open & Blocked by Hose When Personnel Attempted to Perform Routine Flush on RE-1878.Caused by Personnel Error.Personnel Counseled
ML20028B2281982-11-16016 November 1982
LER 82-053/03L-0:on 821018,half Trip Alarm on Steam & Feedwater Rupture Control Sys Channel 2 Received Due to Failure of Steam Generator Level Instrument Cabinet Channel 2,24-volt Dc Power Supply.Caused by Component Failure
ML20027E7891982-11-0404 November 1982
Revised LER 82-052/03X-1:on 820928,reactor Quadrant Power Tilt in Wx Quadrant Exceeded Tech Specs.Caused by Xenon Oscillation Producing Large Negative Imbalance.Control Rod Group 7 Borated Out to Reduce Negative Imbalance
ML20027C9551982-10-19019 October 1982
LER 82-049/03L-0:on 820920 & 22,Channels 2 & 3 on Containment post-accident Radiation Monitor Re 4597BA Were Reading High.Caused by Problem in Microprocessor Software. New Set of Software Installed & Faulty Actuator Replaced
ML20027C5381982-10-0404 October 1982
LER 82-045/03L-0:on 820904,auxiliary Feedwater Pump 1-1, Suction Valve FW786 Observed Closed for No Apparent Reason W/O Operator Touching Close Button.Cause Unknown. Valve Reopened
ML20027A9471982-09-0707 September 1982
LER 82-036/03L-0:on 820808,hole Discovered in Fire Barrier Wall Above Door 309.Caused by Snubber EBD125R43 Penetrating Wall Through Pipe Shell.Hole Left by Workers After Work on Snubbers.Fire Watch Established & Hole Filled
ML20052G6651982-05-0707 May 1982
LER 82-020/03L-0:on 820409,while in Mode 6,station Experienced Loss of 120-volt Ac Distribution Panel Y2.Caused by Blown YV2 Inverter Fuse When Short to Ground Occurred During Maint on Control Room Emergency Ventilation Sys
ML20052E6231982-04-30030 April 1982
LER 82-019/01T-0:on 820426,some Steam Generator Tubes Adjacent to Auxiliary Feedwater Header Showed Potential Interaction W/Header Support Sys.Header Found Insecurely Fastened & Damaged.Cause & Corrections Being Investigated
ML20052E8761982-04-29029 April 1982
LER 82-016/03X-1:on 820312,door 108 Found W/Both Door Closure Mechanisms Broken.Caused by Improper Operation of Door Closure Mechanisms by Personnel.Mechanisms Temporarily Repaired & New Parts Ordered
ML20052C4151982-04-23023 April 1982
LER 82-018/03L-0:on 820326,electrician Cut High Voltage Cable on Source Range Detector NI-2,while Working in Containment Penetration Box P1L1L1.Caused by Problem in Coordination of Work Performed.Cut Cable Reconnected
1993-07-30
[Table view]
Category:RO)
MONTHYEARML20046C0661993-07-30030 July 1993
LER 92-009-01:on 920910,deficiencies Discovered During Dynamic Testing of Motor Operated Valves in Response to Generic Ltr 89-10.MOVs W/Deficiencies Modified or Repaired. W/930730 Ltr
ML20046B6011993-07-26026 July 1993
LER 93-004-00:on 930428,plant Entered Mode 2 W/Afw Pump Turbine Main Steam Line Crossover Check Valve MS735 in Open Position.Caused by Inappropriate Use of Engineering Judgement.Valve MS735 closed.W/930726 Ltr
ML20045D2451993-06-17017 June 1993
LER 93-003-00:on 930520,plant Experienced Trip from Approx & Continuity Between Fuse & Fuseholder Lost,Resulting in Loss of Selected RCS Average Temp Input to Ics.Faulty Fuse Cap & Fuse replaced.W/930617 Ltr
ML20044B1681990-07-10010 July 1990
LER 90-002-01:on 900126,reactor Coolant Pump Current Monitor Inputs to Sfrcs ACH1 & Reactor Pressure Sys Channel 1 Experienced Reactor Trip.Probably Caused by Inadequate Test Switches & Isolation plug.W/900710 Ltr
ML20043H3201990-06-18018 June 1990
LER 90-010-00:on 900518,station Experienced Inadvertent Safety Features Actuation Signal Level 1-4 Actuation W/Injection of 1,000 Gallons of Borated Water.Caused by Loss of 120-volt Ac Bus Y3.W/900618 Ltr
ML20043B5711990-05-25025 May 1990
LER 90-008-00:on 900425,safety Features Actuation Sys Level 1 Actuation Occurred,Resulting in Trip of Containment Radiation Monitors.Caused by High Radiation Fields While Lifting Core Support Assembly.Mod initiated.W/900525 Ltr
ML20043B8051990-05-25025 May 1990
LER 90-009-00:on 900426,source-check of Station Vent Radiation Monitors Not Performed Per Tech Spec 3.3.3.10. Caused by Use of Outmoded Light Emitting Dioide as Check Source.Source Check Procedures revised.W/900525 Ltr
ML20042F2811990-05-0303 May 1990
LER 90-007-00:on 900403,inadvertent,inconsequential Safety Features Actuation Signal Occured While Defueled.Caused by Incidental Contact W/Monitor in Containment.Temporary Barriers Built Around monitors.W/900503 Ltr
ML20042F2791990-05-0303 May 1990
LER 90-006-00:on 900403,station Experienced Safety Features Actuation Sys Levels 1 Through 5 Actuation.Caused by Contact W/Breaker Switch HAAE2 in High Voltage Switchgear Room 2. Meetings Held W/Craft personnel.W/900503 Ltr
ML20042E4891990-04-16016 April 1990
LER 90-005-00:on 900314,determined That Some Class 1E Circuits That Pass Through Containment Electrical Penetrations Do Not Have Adequate Backup Fault Protection. Caused by Inadequate Design control.W/900416 Ltr
ML20012D0341990-03-19019 March 1990
LER 90-004-00:on 900217,fuel Assembly Moved in Spent Fuel Pool While Emergency Ventilation Inoperable.Caused by Personnel Error.Personnel Involved Counseled & Subj LER Part of Required reading.W/900319 Ltr
ML20012C7151990-03-14014 March 1990
LER 90-003-00:on 900212,station Entered Mode 6,refueling,w/o Operable Audible Source Range Indication.Caused by Personnel Error.Individual counseled.W/900314 Ltr
ML20012B4851990-03-0606 March 1990
LER 83-039/03X-2:on 830726,discovered That Handwheel for Inner Door of Personnel Airlock in Shut Position & Partially Opened.Caused by Excessive Use of Door During Outages.Door Repaired & Returned to Operable status.W/900306 Ltr
ML20011F3831990-02-26026 February 1990
LER 90-002-00:on 900126,reactor Tripped from 73% Power. Caused by Spurious Reactor Coolant Pump Monitor Signal Indicating Only One Pump Running in Each Loop.Pump Seal to Be Replaced During Sixth Refueling outage.W/900226 Ltr
ML20006E6861990-02-20020 February 1990
LER 90-001-00:on 900118,reactor Protection Sys Channel 2 Bypassed Temporarily During Performance of DB-MI-03207. Caused by Inadequate Procedure Re Inoperable Channel Removal.Procedure SP1105.02 revised.W/900220 Ltr
ML20011E2251990-01-30030 January 1990
LER 86-032-01:on 860802,inadvertent Start of High Pressure Injection Pump 1-2 Occurred.Caused by Open Relay Coil. Failed Relay Replaced & Procedure Change Initiated. W/900130 Ltr
ML20005G1091990-01-0909 January 1990
LER 89-015-01:on 891026,concluded That Transmitter Was Out of Tolerance When Reactor Protection Sys Channel 2 Returned to Operable Status on 890924.Caused by leak-by in Instrument Manifold.Transmitter Recalibr successfully.W/900109 Ltr
ML20042D4011990-01-0202 January 1990
LER 89-010-01:on 890612,control Room Ventilation Sys Declared Inoperable Due to Compressor High Pressure Trips. Caused by Tripping of Refrigerant Pressure Switch on High Pressure.Switch Reset & Sys retested.W/900102 Ltr
ML19354D7361989-12-22022 December 1989
LER 89-018-00:on 891123,hydrogen Dilution Blower 1-1 Casing Drain Line Broke Off at Casing,Declaring Blower Inoperable. Caused by Drain Line Being Accidentally Stepped On.Drain Removed & Pipe Plug installed.W/891222 Ltr
ML19332F8951989-12-13013 December 1989
LER 89-017-00:on 891113,containment Spray Pump 1-1 Inadvertently Started During Monthly Functional Test in Safety Features Actuation Sys (Sfas) Channel 1.Caused by Failed Relay in Sfas Channel 3.Relay replaced.W/891213 Ltr
ML19332E7521989-12-0404 December 1989
LER 89-016-00:on 890917,unplanned Release of Radioactive Resin to Onsite Settling Basin Occurred.Caused by Personnel Error.Standing Order 89-051 Generated on 890920 to Direct Use of Working Copy of procedures.W/891204 Ltr
ML19332D3111989-11-27027 November 1989
LER 89-015-00:on 890924,RCS Flow Transmitter Out of Tolerance When Reactor Protection Sys Channel 2 Returned to Operable Status.Caused by leak-by in Instrument Manifold Seen as Zero Shift.Transmitter recalibr.W/891127 Ltr
ML19324C2081989-11-10010 November 1989
LER 89-014-00:on 891011,plastic Sheeting Blocked Off Fire Detectors in Auxiliary Feedwater Pump 1-1 Room & High Voltage Switchgear Room B,Making Fire Detectors Inoperable. Caused by Personnel Oversight.Event reviewed.W/891110 Ltr
ML19325D4671989-10-16016 October 1989
LER 89-004-01:on 890411,determined That Circulating Water Line Break Would Result in Loss of Svc Water as Result of Concerns Raised on 890206.Cause Unknown.Standing Order 89-026 in Place to Plug Floor drains.W/891016 Ltr
ML19325C8531989-10-13013 October 1989
LER 89-013-00:on 890913,hourly Fire Watch Patrol Exceeded Allowed Interval,Violating Tech Spec 3.7.10,Action a.2. Caused by Personnel Error.Individual Counseled & Event Info Distributed to Fire Watch personnel.W/891013 Ltr
ML20024E2591983-08-0101 August 1983
LER 83-033/03L-0:on 830620,fire Detection Zone Reactor Coolant Pump 1-2,containment Level 603 Ft Alarmed & Could Not Be Reset.Caused by Faulty Detector String.Zone Will Be Restored During Next Refueling outage.W/830801 Ltr
ML20024B8351983-07-0101 July 1983
LER 83-028/03L-0:on 830603 & 17,fuel Handling Area Radiation Monitors RE8446 & 7 Found Deenergized.Caused by Blown Radiation Monitoring Cabinet Fuse.Fuse replaced.W/830701 Ltr
ML20024B0471983-06-21021 June 1983
LER 83-026/03L-0:on 830524,one Half Channel Trip in Steam & Feedwater Rupture Control Sys (Sfrcs) Channel 2 Received. Caused by Component Failure.Input Buffer replaced.W/830621 Ltr
ML20024A3621983-06-0909 June 1983
LER 83-024/03L-0:on 830511,while Starting Up from 830510 Reactor Trip,Quadrant Power Tilt in Quadrant Yz Exceeded Tech Spec steady-state Limit.Caused by Inherent Design of B&W NSSS & Negative Moderator Temp coefficient.W/830609 Ltr
ML20024A5341983-06-0808 June 1983
LER 83-023/03L-0:on 830510,120-volt Ac Essential Bus Y4 Lost,Resulting in Deenergizing Reactor Protection & Safety Features Actuation Sys Channel 4.Caused by Blown Fuse in Inverter YV4.Power Restored to bus.W/830608 Ltr
ML20024A5481983-06-0707 June 1983
Revised LER 83-002/03X-2:on 830115,18,0409,10 & 0510,RCS Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Slight Fission Product Leakage Through Fuel Cladding.Level of I-131 monitored.W/830607 Ltr
ML20023D9051983-05-26026 May 1983
LER 83-027/03L-0:on 830428,valve RC240B Would Not Close W/O Repeated Signals from Control Room.Caused by Valve Operator Torquing Out Due to Dirty & Improperly Lubricated Stem.Stem Cleaned & Torque Switch reset.W/830526 Ltr
ML20023C3241983-05-0505 May 1983
LER 83-016/03L-0:on 830407,determined That Amplifier of Startup Level Transmitter LT-SP9A3 for Steam Generator 1-2 Failed.Caused by Component Failure within Amplifier. Amplifier Replaced
ML20023C3021983-05-0505 May 1983
Revised LER 83-002/03X-1:on 830115,RCS Dose Equivalent I-131 Exceeded Tech Spec Limit of 1.0 Uci/Gm.Caused by Leakage of Fission Products Through Fuel cladding.I-131 Monitored Until Level Dropped
ML20028E9581983-01-19019 January 1983
LER 82-068/03L-0:on 821220,core Imbalance Vs Core Power Limit Computer Alarm C963 Inoperable.Caused by Mistake in Alarm Subroutine.Alarm Statement Corrected So Limits & Value for Imbalance Scaled Same
ML20028D2291983-01-0707 January 1983
Revised LER 81-045/03X-1:on 810730,after Unit Trip,Three Action Statements Entered.Auxiliary Feedwater Pump 1-2 Did Not Operate Properly.Shield Bldg Integrity Lost When Panel Blown Out.Main Steam Safety Valve Lifted at Low Setpoint
ML20028C1231983-01-0303 January 1983
LER 82-064/03L-0:on 821129,decay Heat Cooler Component Cooling Water Outlet Valve on CCW Train 1 Would Not Open. Caused by Mfg Error.Flanged Bearing Missing from Actuator Mounting Plate.Flanged Bearing Installed on 821215
ML20028C3111982-12-30030 December 1982
Revised LER 81-031/03X-6:on 810512,following Reactor Trip, RCS Sample Level Peaked Above Microcurie Limit.Other Iodine Spikes Occurred 810730,0902,1016 & 23 & 1228.Caused by Slight Leakage of Fission Products Through Fuel Cladding
ML20028C1971982-12-30030 December 1982
Revised LER 82-045/03X-1:on 820904 & 1203,auxiliary Feedwater Pump 1-1 Suction Valve FW786 Closed for No Apparent Reason W/O Operator Touching Close Button.Cause Unknown.Valve FW786 Reopened Upon Discovery
ML20028C2591982-12-30030 December 1982
LER 82-065/03L-0:on 821201,discovered That Control Room Not Placed in Recirculation Mode within 1 H of Ventilation Sys Chlorine Detector Being Taken Out of Svc.On 821203,chlorine Detector Failed.Caused by Personnel Error
ML20028B0291982-11-19019 November 1982
LER 82-054/03L-0:on 821021,Door 107 to Radiation Equipment Found Partially Open & Blocked by Hose When Personnel Attempted to Perform Routine Flush on RE-1878.Caused by Personnel Error.Personnel Counseled
ML20028B2281982-11-16016 November 1982
LER 82-053/03L-0:on 821018,half Trip Alarm on Steam & Feedwater Rupture Control Sys Channel 2 Received Due to Failure of Steam Generator Level Instrument Cabinet Channel 2,24-volt Dc Power Supply.Caused by Component Failure
ML20027E7891982-11-0404 November 1982
Revised LER 82-052/03X-1:on 820928,reactor Quadrant Power Tilt in Wx Quadrant Exceeded Tech Specs.Caused by Xenon Oscillation Producing Large Negative Imbalance.Control Rod Group 7 Borated Out to Reduce Negative Imbalance
ML20027C9551982-10-19019 October 1982
LER 82-049/03L-0:on 820920 & 22,Channels 2 & 3 on Containment post-accident Radiation Monitor Re 4597BA Were Reading High.Caused by Problem in Microprocessor Software. New Set of Software Installed & Faulty Actuator Replaced
ML20027C5381982-10-0404 October 1982
LER 82-045/03L-0:on 820904,auxiliary Feedwater Pump 1-1, Suction Valve FW786 Observed Closed for No Apparent Reason W/O Operator Touching Close Button.Cause Unknown. Valve Reopened
ML20027A9471982-09-0707 September 1982
LER 82-036/03L-0:on 820808,hole Discovered in Fire Barrier Wall Above Door 309.Caused by Snubber EBD125R43 Penetrating Wall Through Pipe Shell.Hole Left by Workers After Work on Snubbers.Fire Watch Established & Hole Filled
ML20052G6651982-05-0707 May 1982
LER 82-020/03L-0:on 820409,while in Mode 6,station Experienced Loss of 120-volt Ac Distribution Panel Y2.Caused by Blown YV2 Inverter Fuse When Short to Ground Occurred During Maint on Control Room Emergency Ventilation Sys
ML20052E6231982-04-30030 April 1982
LER 82-019/01T-0:on 820426,some Steam Generator Tubes Adjacent to Auxiliary Feedwater Header Showed Potential Interaction W/Header Support Sys.Header Found Insecurely Fastened & Damaged.Cause & Corrections Being Investigated
ML20052E8761982-04-29029 April 1982
LER 82-016/03X-1:on 820312,door 108 Found W/Both Door Closure Mechanisms Broken.Caused by Improper Operation of Door Closure Mechanisms by Personnel.Mechanisms Temporarily Repaired & New Parts Ordered
ML20052C4151982-04-23023 April 1982
LER 82-018/03L-0:on 820326,electrician Cut High Voltage Cable on Source Range Detector NI-2,while Working in Containment Penetration Box P1L1L1.Caused by Problem in Coordination of Work Performed.Cut Cable Reconnected
1993-07-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999
Revised Positions for DBNPS & Pnpp QA Program
ML20217D5441999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With
ML20211R0811999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20211B0271999-08-13013 August 1999
SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1
ML20210Q8541999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20209E6231999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20195K2871999-06-16016 June 1999
Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20195F4871999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20207E8011999-05-19019 May 1999
Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project
ML20207F4351999-05-0404 May 1999
Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504
ML20206M6341999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With
ML20205M2931999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With
ML20207J1461999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20199H5931999-01-20020 January 1999
Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant
ML20204J6751998-12-31031 December 1998
1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2
ML20199E2501998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20206B0101998-12-31031 December 1998
1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl
ML20205K5781998-12-31031 December 1998
Waterhammer Phenomena in Containment Air Cooler Swss
ML20197J3441998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20195D0001998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20155B6781998-10-28028 October 1998
Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process
ML20154H5801998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20151W1611998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Dbnps.With
ML20237E3171998-08-21021 August 1998
ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station
ML20237B1681998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20236U5011998-07-23023 July 1998
Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event
ML20236R1441998-07-15015 July 1998
SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1
ML20236N7451998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20236K3981998-06-30030 June 1998
SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1
ML20236K5131998-06-29029 June 1998
Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20249A4121998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20196B5221998-05-23023 May 1998
10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523
ML20236E7581998-05-19019 May 1998
Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr
ML20236N7501998-04-30030 April 1998
Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit
ML20247F6721998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1
ML20249A4141998-04-30030 April 1998
Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20217P8041998-04-0707 April 1998
11RFO OTSG ECT Insp Scope
ML20216B4041998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20216C5131998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20202D3721998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20199G6321998-01-26026 January 1998
Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR
ML20198R4771998-01-13013 January 1998
SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1
ML20198K7931997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1
ML20217K6401997-12-31031 December 1997
1997 Annual Rept First Energy
ML20203A3931997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1
ML20198S5371997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station
ML20217H7701997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1
ML20216H3261997-08-31031 August 1997
Monthly Operating Rept for August 1997 for DBNPS
ML20217K0241997-07-31031 July 1997
Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1
1999-09-30
[Table view] |
Text
u.m em . ,- ,
LtdENSEE EVENT REPORT f-gv)
CONTr.0L BLOCK: l 1
l l l l 6
lh (PLE ASE PRINT OR T'. ELL RECUIRED INFORMATION) l 01 Hj Dl Bl Sl 1l@l0 l0 l- l0 l0 lN lP IF l IO l1-25l@!264 I 1UCENSE l 1 !TYPE 1 l JG1 lh!_ l SSl@
57 .;AT 7 3 LICENSEE CCDE 14 15 LICENSE NuMS ER CO lol11. ERCI I L l@l 0 15 10 l- 10 13 14 16 @ l0 16 [0 14 17 i8 l@l0l612181 64 63 EV ENT D ATg 74 75 REPORT QATE 80 I 8 60 61 COCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 21 l On '6/4/78 while perforr.ing surveillance testing, Diesel Generator (DG) 1-1 failed to l
[o !al l Operate with proper frequency and voltage. The test was suspended and DG l-1 declaredl Io Ie 1 l inoperable. The unit was in Mode 6 at the ti=c of the occurrence. This incident is l Io isi I being reported as a component failure. There was no danger to the health and safety [
i l o 16 j l of the public or unit personnel. Diesel Generator 1-2 was operable had e=ergency (NP-33-78-74) l I O l 7 l l power been required.
I l o l e I 'l __ 80 CAUSE COMP. VALVE SYSTEM CAUSE CCOE SU8 CODE COMPONENT CODE SUSCCOE SUSCODE CODE lo191 lE l3 j @ lE l@ l A l@ lG lE IN lE IR l A lh lD lh l Zlh 12 18 19 20 7 8 9 10 ft 12 4EVISION SEOUENTI AL OCCURRENCE REPORT REPORT NO. CODE TYPE NC.
EVENT YEAR
,_ 21 22 1-1 23 10 !6 l2 I 24 26 W27 I 01 31 23 29 W
30 1-l 31 I 0l 32 ME M HOURS 22 5 8 i C FOR 8. SUPPLi$ MANUFAC RER EN 'ACT ON CN PLANT
,)lAj@lZj@ l Z [g l36Z lg 3l10 l0 l0 l- 40 l lY lg 41 lY lg 42 l43A l@ lP l3 l1 [8 l]
64 47 33 34 35 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS f
ji joll The cause of this occurrence can be attributed to a cennonent failure of a ortra n lt ; i j l potential fuse for the diesel generator. The crimarv cotential fuse for DC 1-1 v w I
,,,7, l replaced. At 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on 6/4/78, the Diesel Generator Monthlv Test was ececleted I I
l3 ;3j l and the diesel generator declared operable.
I li !4 l l 7 8 9
% POWER OTHER STATUS O50 Y DtScoVERY DESCRIFTioN ST l
(1 ! *5l' l G lh l 0l Ol OlhlNA l l3l@lSurveillanceTestST 5031.07 so
' 12 n 4A . 45 46 ACTiv Tv Co'0 TENT AMOUNT CF ACTIVITY LOCATION OF RELEASE RELEASED OF RELEASE NA l l NA l
}1 l6l 7 8 9 l Zl@ lZ 10 11 A4 45 80 PERSONNEL EXPCSURES
- NuveER TV8E DESCRIPTION 39
_ a g t,i l l1 l7ll0l0l0 lZ A PERSONNE L INJURIES Q Ag ge.,i p NUv9ER DESCRIPTION l
ii n i 10 ! Q i O t1l@l 12NA (\*,,.[ s:
7 (' % 9
( , w' ;r$== """ @ '
8oo127o/o3 l ms i Z igi NA 83 d 9 10 7
'U B L ICITY NRC USE CNLY ISSUED DE SC R f PTION l ll l l l Il III IIly}
l l 0 } l N l 44 'l NA 63 69 80 ,
10 .
7 a 3 ~
I F 3**19? PwCNE: 51 ~ 2 50- SOMI -
I- 2 '; '
, , , , , . 33, N AME 05 PREP t.R ER
.___ -- . _ - - .- - .- - . - . - . _ . - - _ . . - .__.=. _... ._ .
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TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER UP-33-78-74 l DATE OF EVENT: June 4, 1978 FACILITY: Davis-Besse Unit 1 ,
f
- IDENTIFICATION OF OCCURRENCE
- Diesel Generator 1-1 declared inoperable on June 4, 1978.
l l Conditions Prior to Occurrence: The unit was in Mode 6., with Power (5"I) = 0 and Load (M4E) = 0, a
Description of Occurrence: At 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on June 4,1978, while performing Surveil-l
- lance Test ST 5031.07, " Safety Features Actuation System (SFAS) 18 Month or Refuel-ing Test" Diesel Generator 1-1 came up to speed but the generator breaker did not j
close. The test was suspended at this point, and Surveillance Test ST 5081.01,
- " Diesel Generator Monthly Test", was performed. Upon starting Diesel Generator 1-1, l l the frequency was' not stable and the generator voltage was icw. The test was sus- ,
pended at this point, and the diesel generator declared inoperable.
This occurrence did not place the unit in the Action Statement: of Technical Speci-fication 3.8.1.2 because the unit was in Mode 6, which requires only one diesel generator to be operable while in Modes 5 or 6. This incident is being reported as a component failyss.
Designation of Aeoarent Cause of Occurrence: The cause of this occurrence can be i attributed to a component failure of a primary potential fuse for the diesel generator.
Analysis of Occurrence: . There was no danger to the health and safety of the public or to unit personnel. Diesel Generator 1-1 was not required for emergency power during the period of time it was inoperable.- Diesel Generator 1-2 was operable
had emergency power been required. ,
j Corrective Action: Under Maintenance Work Order 78-1332, the primary potential fuse for Diesel Generator 1-1 wcs replaced.
4 At 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on June 4,1978, Surveillance Test ST 5081.01, Diesel Generator Monthly Test, was completed and the diesel generator declared operable.
1 ,
Fa i lure Data: No previous si=ilar events have occurred.
4 LER #78-062
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