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| {{#Wiki_filter:,,,,c-_,,,,_ . _ . . - - . . _ . . . . . | | {{#Wiki_filter:,,,,c-_,,,, _ . _ . . - - . . _ . . . . . .. |
| ..f7 77 t LICENSEE EVENT REPORT | | f7 77 t LICENSEE EVENT REPORT CONTROL BLOCK- l l l l l l - fPLEASE PRINT OR TYPE AL'. REQU! RED INFORMATIOen. |
| .CONTROL BLOCK- l lllll-fPLEASE PRINT OR TYPE AL'. REQU! RED INFORMATIOen
| | i 6 l se[g I o ( 1 [ l uuCENsu |
| .i 6 I o ( 1 [ l u J g i c ! c l n l p l@l 0 Iq!_[0[qjolql0l_l9[o(@l4[1 [] (1l'al@32 l
| | , 3 J gCCE i c ! cal n l p l@l 0 Iq!_[0[qjolql0l_l9[o(@l4[1 |
| [g ,-3 uCENsu CCE a , t.cem NuwEs n 2s scENsE m :
| | , t.cem NuwEs n 2s |
| c.u se 2 , CON'T___E !L @lJl5I0101013l112 @l0l310131719 @l0 !o l? ll l 7 lc l@
| | [] (1l'al@32 c.u scENsE m : |
| _', I'a 60 61 DOCKET NUMBER 68 69 EVENT DATE M 75 REPORT DATE 80 EVENT DESCRfPTION AND PROBABLE CONSEQUENCES h
| | 2 CON'T _ __ |
| -a ,! Durina a turbine roll with the reactor at 3*.
| | ', I |
| P'.B containment carticulate and | | ' a E !L @lJl5I0101013l112 @l0l310131719 @l0 !o l? ll l 7 lc l@ |
| !o.l caseous monitor was rendered inocerable by a blown fuse. The plant start-uo lo ,3 Ti'-] I was stopped and ocwer was reduced to hot standbv at 0750 (Mode 3). The carticulate 1 i a.vi casecus monitor system was returned to service at 0853 on 8/3/79. The contain-lois I rrent sumo level alant remained in service throuchaut this event (T.S.3.4.6.1.).
| | 60 61 DOCKET NUMBER 68 69 EVENT DATE M 75 REPORT DATE 80 |
| i 0,s o,7 i This is not a repetitive occurrence. | | - a EVENT DESCRfPTION AND PROBABLE CONSEQUENCES h , |
| I IO88l!50 , g g SYS'EM CA US E CAUSE COM*.VALvf CCCE CODE.SueCCDE COM*CNENT CODE SUBCODE SveGODE Ol9llllllllf!!lll-llllf 7 8 9 10 11 12 13 18 1s 20 SE QUE NTIA L OCCU A AENCE REFOR7 REvtSION CODE'JPE~c q. AC ENTVEAR AEP T.h',ENa'{l7j9l l __ [l0l- l], ll0 l 3 )lj __llj m 21 22 0.3 24 26 27 20 29 30 31 32 ACTION F LrruR E EFFECT SHUTDOW?e AT*ACHMENT NPR:).4 PAIME COPM. | | : o. ! Durina a turbine roll with the reactor at 3*. P'.B containment carticulate and ! |
| COMPOPffNT TAKEN ACTION 04 PLANT METHOD HOURS u SUBMfTTED FORubuB.SUP*LI E R MANUFACTURER lXl@l Al@ISl@[ A l@l0 l0 l01/ l | | o ,3 l caseous monitor was rendered inocerable by a blown fuse. The plant start-uo l Ti'-] I was stopped and ocwer was reduced to hot standbv at 0750 (Mode 3). The carticulate 1 ois i a.vi casecus monitor system was returned to service at 0853 on 8/3/79. The contain- l 0,s I rrent sumo level alant remained in service throuchaut this event (T.S.3.4.6.1.). i o,7 i This is not a repetitive occurrence. I IO88 l ! |
| [Y @N]@l A j@{W l1 12 l0 l@ | | g g 50 SYS'EM CA US E CAUSE COM*. VALvf CCCE CODE. SueCCDE COM*CNENT CODE SUBCODE SveGODE Ol9l l l l l l l l f ! ! l l l- l l l l f 7 8 9 10 11 12 13 18 1s 20 SE QUE NTIA L OCCU A AENCE REFOR7 REvtSION ENTVEAR AEP T CODE c q. AC . |
| 3J 34 35 36 3?40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i : o l l The initial cause of event was a blown neutral onase fuse for- the affected cabinet's Il control cower. Durinn reclaterent, a fuse brcke in the holder. | | 'JPE ~ |
| E# forts to rmeve a f i3 , - ,- I fuse end cao danaced the holder such that holder was shorted to around. | | h',ENa'{l7j9l l __ [ l0 24 l- l ], l l0 l 3 ) |
| Initiall3,,3i [ correcdve action consisted of liftino field cables to isolate circuits cowered from 1
| | 29 30 m |
| ,~.3"-.' i g I this source ,'10 faults were found on these circuits.(See attachrent' sheet).
| | l j __l l j 21 22 0.3 26 27 20 31 32 ACTION F LrruR E EFFECT SHUTDOW?e AT*ACHMENT NPR:).4 PAIME COPM. COMPOPffNT TAKEN ACTION 04 PLANT METHOD HOURS u SUBMfTTED FORubuB. SUP*LI E R MANUFACTURER lXl@l Al@ ISl@ [36A l@ l0 l0 l01/ l [Y @ N]@ l A j@ {W l1 12 l047l@ |
| -I'~80*8 9'-r S ATus N POWE A OTHER $TA TUS ~
| | 3J 34 35 3? 40 41 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i : o l l The initial cause of event was a blown neutral onase fuse for- the affected cabinet's I i3 l control cower. Durinn reclaterent, a fuse brcke in the holder. E# forts to rmeve a f |
| 'I. N OF'F ACILITV '
| | , - ,- I fuse end cao danaced the holder such that holder was shorted to around. Initial l 3,,3i [ correcdve action consisted of liftino field cables to isolate circuits cowered from 1 , |
| DisCCVERY Ut3COVERY OESCHiPHOM, 1 ,5 j Cl@ l0 l0 [3 l@[ | | 3"-. |
| NAll A l@j Goerator Observation
| | '10 faults were found on these circuits. |
| -[.A co'ArEnT..q " /
| | ~ |
| ''"'" ' 4'''8. so-l ! 2 i @ l Z T@l PA. t!~y .,. _ , ,-' . tcCAT os OP etacE h- V
| | (See attachrent' sheet). |
| ,._'._, q"-' ''v.ACuviTv auceNT er acu viTv h ,--~-- atuasm or asuAst- -
| | ~ |
| .-.=Dl;,t , a 9 m n u n.a0***Sor4NE L E XPOSUR E 0 | | ' i g 8I 9this source , 80* |
| _ , y .aea | | I' F ACILITV ' -r 'I. N OF ' |
| !gl n' h;c, I. :EsCmanc3 _
| | S ATus N POWE A OTHER $TA TUS ~ DisCCVERY Ut3COVERY OESCHiPHOM, 1 ,5 j Cl@ l0 l0 [3 l@[ NA l l A l@j Goerator Observation - |
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| 7009060 2Q | | .= |
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| ~(I MdWDM'sAvt cc PaEPARER pscar--. | | ***Sor4NE L E XPOSUR E 0 |
| ,_._..._. ._...LER NO. 79-029/3L
| | _ , y .aea . :EsCmanc3 _ |
| , DOCKET NO. 50-318
| | Q'-i- !gl Qj n' h;c, I , |
| ~EVENT DATE 08-03-79 _
| | * l s , n 2 a w |
| _.REPORT DATE 08-31-79 | | " M w FL *. # ES ,q |
| -ST_.T.A_CHME NT
| | !] 3 ' |
| ..___---.CAUSE DESCR!? TION A?!D CORRECTIVE ACTIONS:
| | 01 C[0 @[~~ NA l |
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| | |
| | LER NO. 79-029/3L , |
| | DOCKET NO. 50-318 ~ |
| | EVENT DATE 08-03-79 _ _. |
| | REPORT DATE 08-31-79 - |
| | ST_.T.A_CHME NT CAUSE DESCR!? TION A?!D CORRECTIVE ACTIONS: |
| Uoon discovery of the damaced Mrse holder, the holder was jumpered and Contml Power was restored. A replacement holder is on order and will be installed wnen received. Maintenance Recuest 0-79-2353 is beine held oren for completion of repair. | | Uoon discovery of the damaced Mrse holder, the holder was jumpered and Contml Power was restored. A replacement holder is on order and will be installed wnen received. Maintenance Recuest 0-79-2353 is beine held oren for completion of repair. |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17326A2011999-08-23023 August 1999
LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr
ML20029C7321994-04-22022 April 1994
LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr
ML20046B4731993-07-30030 July 1993
LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr
ML20046A4911993-07-22022 July 1993
LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr
ML20045G8611993-07-0909 July 1993
LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr
ML20045G7281993-07-0808 July 1993
LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr
ML20045G8661993-07-0808 July 1993
LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr
ML20045E7361993-06-29029 June 1993
LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr
ML20029B1261991-02-28028 February 1991
LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr
ML20028H8011991-01-24024 January 1991
LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr
ML20044A1861990-06-20020 June 1990
LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr
ML20043G1071990-06-13013 June 1990
LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr
ML20043F1221990-06-0404 June 1990
LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr
ML20043A7871990-05-21021 May 1990
LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr
ML20043A3441990-05-14014 May 1990
LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr
ML20043A3401990-05-14014 May 1990
LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr
ML20042G4521990-05-0707 May 1990
LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr
ML20042F5801990-05-0404 May 1990
LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr
ML20012E9931990-03-29029 March 1990
LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr
ML20012F0001990-03-28028 March 1990
LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr
ML20012E9951990-03-28028 March 1990
LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr
ML20012E0101990-03-26026 March 1990
LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr
ML20012C4971990-03-15015 March 1990
LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr
ML20012C4861990-03-12012 March 1990
LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr
ML20012B8991990-03-12012 March 1990
LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr
ML20012B4221990-03-0606 March 1990
LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr
ML20011F2701990-02-27027 February 1990
LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr
ML20011F2091990-02-27027 February 1990
LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr
ML20006F8601990-02-22022 February 1990
LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr
ML20006E0521990-02-0808 February 1990
LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr
ML20006B4801990-01-26026 January 1990
LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr
ML19354D8931990-01-17017 January 1990
LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr
ML20005F1921990-01-10010 January 1990
LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr
ML20005E3971989-12-28028 December 1989
LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr
ML19351A4551989-12-13013 December 1989
LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr
ML20005D6611989-12-0606 December 1989
LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr
ML19325F3951989-11-10010 November 1989
LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr
ML19325E8221989-11-0303 November 1989
LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr
ML19324B2511989-10-27027 October 1989
LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr
ML19325C3281989-10-10010 October 1989
LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr
ML19325C3701989-10-0909 October 1989
LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr
ML20024F3771983-08-25025 August 1983
LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr
ML20024F5731983-08-25025 August 1983
LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr
ML20024E6761983-08-0404 August 1983
Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr
ML20024E1721983-07-14014 July 1983
Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr
ML20024D0071983-07-0808 July 1983
LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr
ML20024D0091983-07-0808 July 1983
LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr
ML20024B8231983-06-23023 June 1983
LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr
ML20024C0141983-06-22022 June 1983
Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr
ML20024A8881983-06-16016 June 1983
LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr
1999-08-23
[Table view]
Category:RO)
MONTHYEARML17326A2011999-08-23023 August 1999
LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr
ML20029C7321994-04-22022 April 1994
LER 94-004-00:on 940221,discovered Corrosion of Three Nuts on One of Incor Instrumentation Reactor Vessel Head.Caused by Increase of Wet Boric Acid.Leaking Flanges Repaired.W/ 940422 Ltr
ML20046B4731993-07-30030 July 1993
LER 93-005-00:on 930630,TS 3.0.3 Entered Due to Both Containment Spray Sys Inoperable.Replaced CCW Outlet Valve Actuator Connecting Link Assembly from Number 11 SDC Heat exchanger.W/930730 Ltr
ML20046A4911993-07-22022 July 1993
LER 93-003-00:on 930625,SG Tripped Due to Low Water Level. Caused by Insufficient Feedwater Addition Due to Inadequate Communication.Reemphasis on Improved Communication Stressed. W/930722 Ltr
ML20045G8611993-07-0909 July 1993
LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr
ML20045G7281993-07-0808 July 1993
LER 93-002-00:on 930608,inadvertent Arw Actuation Sys & RPS Actuations Experienced During Performance of Awf Sys Large Flow Surveillance Testing.Caused by Failure to Note Differential Pressure Condition.Valve opened.W/930708 Ltr
ML20045G8661993-07-0808 July 1993
LER 93-004-00:on 930611,reactor Tripped Due to Turbine Trip Resulting from Inadequate Procedure.Procedure Changes Made to Open Appropriate FW Heater High Level Dump Valves During Plant startup.W/930708 Ltr
ML20045E7361993-06-29029 June 1993
LER 93-002-01:on 930205,software Vendor Discovered Error in User Manual for Updating Basss data-input Library.Caused by Failure of QA Procedures to Require Independent Review of User Manuals.Manual Surveillances performed.W/930629 Ltr
ML20029B1261991-02-28028 February 1991
LER 91-001-00:on 910129,tubing in Air Start Sys for Emergency Diesel Generator Failed During Seismic Event. Caused by Error in Design of EDG Air Start Sys.Permanent Mod to Sys installed.W/910228 Ltr
ML20028H8011991-01-24024 January 1991
LER 90-002-01:on 900116,determined That 891211 Reconstitution of More than One Spent Fuel Assembly Per Time in Violation of Fuel Handling Incident Safety Analysis. Caused by Deficient procedure.W/910124 Ltr
ML20044A1861990-06-20020 June 1990
LER 87-002-01:on 861203,section of Thin Wall Found on Main Steam Line W/Readings Below Allowable Min of 0.95 Inches. Caused by Grinding of Edge of Pipe to Achieve Proper fit-up for Welding.Relief from IWB-3610 granted.W/900620 Ltr
ML20043G1071990-06-13013 June 1990
LER 89-019-01:on 891128,determined That for Approx 10 Yrs, from 1979-1989,requirement to Lock HPSI Discharge Header Isolation Valves Shut Not Implemented.Caused by Inadequate Mgt Attention.Test Procedures modified.W/900613 Ltr
ML20043F1221990-06-0404 June 1990
LER 90-017-00:on 900505,pin Hole Leak Observed in Discharge Piping of Saltwater Pump 13.Caused by Localized Corrosion. Leaking Spool Piece Removed & Blank Flange Installed. W/900604 Ltr
ML20043A7871990-05-21021 May 1990
LER 90-016-00:on 900421,determined That Waste Gas Decay Tank (Wgdt) 13 Discharged Instead of (Wgdt) 11 for Discharge Permit Issued.Caused by Inadequate Communications.Training Performed for Operators Re event.W/900521 Ltr
ML20043A3441990-05-14014 May 1990
LER 90-014-00:on 900413 & 19,unit Entered Tech Spec Limiting Condition of Operation 3.0.3 Due to Potential Inoperability of Three Out of Four Reactor Protection Sys Delta T Power Channels.Caused by Lack of Procedure guidance.W/900514 Ltr
ML20043A3401990-05-14014 May 1990
LER 90-013-00:on 900413,determined That Axial Shape Index Channels Out of Spec & Inoperable.Caused by Inadequate Understanding of Design Basis for Excore/Incore Comparison. Design Basis for Excore/Incore improved.W/900514 Ltr
ML20042G4521990-05-0707 May 1990
LER 90-015-00:on 900407,discovered That Relay Contact Which Actuates Reactor Trip Breaker Shunt Trip Not Adequately Functionally Tested.Caused by Failure to Examine Circuit in Detail When Test developed.W/900507 Ltr
ML20042F5801990-05-0404 May 1990
LER 90-012-00:on 900406,identified That Procedure for LOCA Would Not Ensure post-LOCA Core Flush Would Be Initiated in Time to Prevent Boron Precipitation.Caused by Personnel Error.Configuration Mgt Program strengthened.W/900504 Ltr
ML20012E9931990-03-29029 March 1990
LER 90-008-00:on 900227,determined That Surveillance Procedure M-280-0 Did Not Include Steps to Fully Test Control Room Recorder for Hydrogen Analyzers.Caused by Personnel Error.Procedure Revised on 900308.W/900329 Ltr
ML20012F0001990-03-28028 March 1990
LER 89-006-01:on 890508,containment Iodine Filters Outside Design Basis Due to Equipment Qualification.Recalculation of Total Integrated Radiation Dose to Cables for Filter Fans Demonstrated Cable qualified.W/900328 Ltr
ML20012E9951990-03-28028 March 1990
LER 89-014-01:on 890723,determined That Salt Water Header Not Capable of Withstanding Seismic Event Intact.Caused by Inadequate Welding of Blind Spool Pieces in Pipe.Insp Revealed Spools Capable as installed.W/900328 Ltr
ML20012E0101990-03-26026 March 1990
LER 90-009-00:on 900224,failure to Meet Action Requirement Re Tech Spec 3.7.12.Caused by Personnel Error.Cables Removed from Doorway in Charging Pump Room & Not Allowed to Be Placed in doorway.W/900326 Ltr
ML20012C4971990-03-15015 March 1990
LER 90-007-00:on 900216,discovered That Supervised Circuits Associated W/Fire Detection Instruments Located in Reactor Coolant Pump Bays Not Been Included in Surveillance Test Procedure.Caused by Personnel error.W/900315 Ltr
ML20012C4861990-03-12012 March 1990
LER 90-006-00:on 900209,determined That Four Fire Dampers Missing.Caused by Not Identifying Penetrations as Requiring Dampers When Fire Hazards Analysis of Plant Conducted.Hourly Fire Watch Continued.Missing Dampers installed.W/900312 Ltr
ML20012B8991990-03-12012 March 1990
LER 89-023-01:on 891220,determined That Pipe Rupture in nonsafety-related Svc Water Subsystem Could Result in Rapid Draining of Subsystems That Serve Auxiliary Bldg.Task Force Formed to Determine Corrective actions.W/900312 Ltr
ML20012B4221990-03-0606 March 1990
LER 89-012-01:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed.Caused by Procedural Deficiency.Procedures Revised to Include Valve & Surveillance Test Program Instruction revised.W/900306 Ltr
ML20011F2701990-02-27027 February 1990
LER 90-001-01:on 900109,determined That Surveillance Tests Used to Perform Channel Calibr Tests for Acoustic Flow Monitoring Devices Inadequate.Caused by Personnel Error & Inadequate Procedures.Swapped Leads restored.W/900227 Ltr
ML20011F2091990-02-27027 February 1990
LER 89-026-00:on 891128,determined That Particulate Levels in Samples Taken from Lower Third of Tanks Exceeded Allowable Limits.Caused by Inadequate Sampling Technique. Tanks Cleaned & Filled W/Clean fuel.W/900227 Ltr
ML20006F8601990-02-22022 February 1990
LER 90-004-00:on 900123,discovered Fire Barrier Penetration Seal Open for Indeterminate Time W/O Performing Tech Spec 3.7.12.a Required Actions.Caused by Personnel Error. Temporary Fire Seal installed.W/900222 Ltr
ML20006E0521990-02-0808 February 1990
LER 90-001-00:on 891221,discovered That Acoustic Indications for One PORV & One Safety Valve Were Reversed During Surveillance Test.Caused by Personnel Error.Swapped Leads Restored to Proper configuration.W/900208 Ltr
ML20006B4801990-01-26026 January 1990
LER 89-022-00:on 891227,core Alterations Performed W/Only One of Two Containment Vent Valves Closed,Violating Tech Specs.Caused by Procedural Deficiency.Surveillance Test Procedure Revised to Include Deleted valves.W/900126 Ltr
ML19354D8931990-01-17017 January 1990
LER 89-024-00:on 891218,determined That Wires Which Connect Actuation Device Logic Relay Contacts to Remainder of Circuit Not Tested During Channel Calibr Test.Caused by Inadequate Test.Test Program Upgrade underway.W/900117 Ltr
ML20005F1921990-01-10010 January 1990
LER 89-025-00:on 891208,Tech Spec Action Statement Entered When Ventilation Ducts Penetrating Fire Barrier Could Not Be Accessed to Determine If Fire Dampers Installed.On 891211, Fire Watch Missed.Caused by Personnel error.W/900110 Ltr
ML20005E3971989-12-28028 December 1989
LER 89-019-00:on 891128,discovered That HPSI Discharge Header Isolation Valves Not Locked Shut When RCS in Water Solid Condition,Resulting in Operation Outside Design Basis. Procedure Revised to Require Valves closed.W/891228 Ltr
ML19351A4551989-12-13013 December 1989
LER 89-020-00:on 891113,determined That Some Solenoid Valves & Valve Power Supplies for Saltwater Sys May Not Be Able to Perform Design Function After Design Basis Seismic Event. Cause Undetermined.Power Supplies upgraded.W/891213 Ltr
ML20005D6611989-12-0606 December 1989
LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr
ML19325F3951989-11-10010 November 1989
LER 89-002-01:on 890228,discovered That Fire Barrier Penetration Inoperable & Action Statement Requirements Not Satisfied.Caused by Inadequate Administrative Controls. Penetration Returned to Operable status.W/891115 Ltr
ML19325E8221989-11-0303 November 1989
LER 89-007-01:on 890505,evidence of Reactor Coolant Leakage from 120 Pressurizer Vessel Heater Penetrations Discovered. Caused by IGSCC of Inconel 600.All Penetrations Using J-welds & Inconel 600 Visually inspected.W/891103 Ltr
ML19324B2511989-10-27027 October 1989
LER 89-012-01:on 890720,discovered That Master Solenoid to Switchgear Room Halon Sys Disconnected Since 890629.Caused by Personnel Error Resulting from Lack of Written Procedure. Procedure Revised to Apply Temporary mods.W/891027 Ltr
ML19325C3281989-10-10010 October 1989
LER 89-016-00:on 890908,determined That as-found Condition of Resistance Temp Detectors Did Not Match Tested Configuration.Cause Not Stated.Subj Detectors Will Be Sealed,Per Environ Qualification requirements.W/891010 Ltr
ML19325C3701989-10-0909 October 1989
LER 89-017-00:on 890907,determined That Discrepancy in Acceptance Criteria of Surveillance Test Procedure M-452-0 Resulted in Failure to Fully Comply W/Requirements of Tech Spec 3.9.12.Main Cause undetermined.W/891009 Ltr
ML20024F3771983-08-25025 August 1983
LER 83-044/03L-0:on 830808,diesel Generator 12 Tripped on Low Jacket Cooling Water Pressure While Verifying Operability.Cause Not Stated.Coolant Jacket Vented & Large Amount of Air Found.No Evidence of leakage.W/830825 Ltr
ML20024F5731983-08-25025 August 1983
LER 83-040/03L-0:on 830727,control Room Air Conditioner 11 Discovered W/Damaged Condenser Fan.Caused by Loose Set Screws Securing Fan in Position.Set Screws Restored. W/830825 Ltr
ML20024E6761983-08-0404 August 1983
Updated LER 83-011/03X-1:on 830207,during Surveillance Testing ESFAS a Logic Sequencer Failed,Rendering Diesel Generator 12 Inoperable.Caused by Intermittent Operation of Module Test Push Button.Part replaced.W/830804 Ltr
ML20024E1721983-07-14014 July 1983
Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr
ML20024D0071983-07-0808 July 1983
LER 83-035/03L-0:on 830610,during Normal Power Operation,Esf Actuation Sys Channel Zg Steam Generator Level Tripped. Caused by Failed Vitro Isolator Module.Module Replaced.W/ 830708 Ltr
ML20024D0091983-07-0808 July 1983
LER 83-033/03L-0:on 830603,fire Detection Instrumentation in Containment Southeast Electrical Penetration Determined Inoperable.Repair Impossible Due to Inaccessability of Protecto wire.W/830708 Ltr
ML20024B8231983-06-23023 June 1983
LER 83-029/03L-0:on 830524,during Normal Operation, Surveillance Testing Indicated Neither Spent Fuel Pool Exhaust Fans 11 or 12 Would Maintain Required Negative Pressure.Caused by Clogged HEPA filters.W/830623 Ltr
ML20024C0141983-06-22022 June 1983
Updated LER 81-080/03X-1:on 811116,discovered Weep from Cracked Weld on Spent Fuel Cooling Pump Discharge Vent Line 12.Caused by Inadequate Support of Vent Line.Support Assembly installed.W/830622 Ltr
ML20024A8881983-06-16016 June 1983
LER 83-032/03L-0:on 830523,containment Isolation Sys B Logic Module Would Not Actuate.Caused by Defective Vitro Labs Std Logic Module.Module Replaced.Failed Module Returned to Vitro Labs for Repair & testing.W/830616 Ltr
1999-08-23
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With
ML20216J8731999-09-10010 September 1999
Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant
ML20212A4441999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with
ML17326A2011999-08-23023 August 1999
LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr
ML20210S6091999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with
ML20210N6001999-07-27027 July 1999
ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included
ML20210B7941999-07-15015 July 1999
SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs
LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999
Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified
ML20209F1721999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With
LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999
Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed
ML20196C6981999-06-21021 June 1999
Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable
ML20195K2811999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with
ML20206R5871999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with
ML20195B3891999-04-30030 April 1999
0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models
ML20205N2951999-04-13013 April 1999
Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored
ML20210T5211999-04-0101 April 1999
Rev 0 to Ccnpp COLR for Unit 2,Cycle 13
ML20205P5441999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With
ML20204H6471999-03-21021 March 1999
SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20207M8321999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With
ML20203D4311999-02-0505 February 1999
Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons
ML20199G4671999-01-20020 January 1999
SER Accepting USI A-46 Implementation for Plant
ML20206Q3221999-01-11011 January 1999
Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104
ML20207L0451999-01-0808 January 1999
Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors
ML20199F4781999-01-0808 January 1999
Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed
ML20198S7591999-01-0707 January 1999
SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20207M2281998-12-31031 December 1998
1998 Annual Rept for Bg&E. with
ML20199E2931998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with
ML20206R9911998-12-0808 December 1998
Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with
ML20198B2631998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With
ML20195H1001998-11-16016 November 1998
Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative
ML20196E2211998-10-31031 October 1998
Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves
ML20195E5281998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With
ML20154Q7191998-10-21021 October 1998
Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation
ML20154G3931998-10-0505 October 1998
Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code
ML20154M5841998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With
ML20153C2571998-09-18018 September 1998
Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925
ML20153C1091998-09-18018 September 1998
Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves
ML20151U5441998-09-0404 September 1998
Bg&E ISI Summary Rept for Calvert Cliffs
ML20151T5281998-09-0101 September 1998
Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced
ML20151Y1191998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With
ML20237D4981998-08-19019 August 1998
Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20237B9371998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant
ML20237D5941998-07-22022 July 1998
Rev 2 to Ccnpp COLR for Unit 2,Cycle 12
ML20236L7521998-07-0606 July 1998
Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness
ML20236F7791998-06-30030 June 1998
Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1
ML20236R0881998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20236X3101998-06-19019 June 1998
Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12
ML20249A9571998-06-15015 June 1998
Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc
ML20249A7711998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2
1999-09-30
[Table view] |
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- o. ! Durina a turbine roll with the reactor at 3*. P'.B containment carticulate and !
o ,3 l caseous monitor was rendered inocerable by a blown fuse. The plant start-uo l Ti'-] I was stopped and ocwer was reduced to hot standbv at 0750 (Mode 3). The carticulate 1 ois i a.vi casecus monitor system was returned to service at 0853 on 8/3/79. The contain- l 0,s I rrent sumo level alant remained in service throuchaut this event (T.S.3.4.6.1.). i o,7 i This is not a repetitive occurrence. I IO88 l !
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3J 34 35 3? 40 41 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i : o l l The initial cause of event was a blown neutral onase fuse for- the affected cabinet's I i3 l control cower. Durinn reclaterent, a fuse brcke in the holder. E# forts to rmeve a f
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EVENT DATE 08-03-79 _ _.
REPORT DATE 08-31-79 -
ST_.T.A_CHME NT CAUSE DESCR!? TION A?!D CORRECTIVE ACTIONS:
Uoon discovery of the damaced Mrse holder, the holder was jumpered and Contml Power was restored. A replacement holder is on order and will be installed wnen received. Maintenance Recuest 0-79-2353 is beine held oren for completion of repair.
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