Similar Documents at Hatch |
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LER-1981-056, /03L-0:on 810610,during Startup,Offgas Hydrogen Analyzer 1N62-N009A Was Reported Inoperative.Caused by Personnel Error.Root Valve N62-F064 a Was Found Closed. Valve Opened |
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U. S. NUCLEAR REGULATCRY COMMISSION l
NRC FORM 366 (7 77)
LICENSEE EVENT REPORT CONVROL BLOCX: l
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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121 l While the olant was in start-uo.1N62-N009A. Off-nan H3 Analyzer was I
lo l3 l l found to be inoperative.
The event date is unknown, but reported in-I l o 14 l l operative on June 10, 1981.
Tech Specs Table 2.1.3.h reouires one coer-l loIsl l able channel.
Redundant Hp Analyzer, IN62-N009B, was operable. P1 ant I
l o 16 I l operation nor the health and safety of the oublic was not affected by I
lol7ll this event.
This is a repetitive event as last reported on Reportable I
ioisi l Occurrenca Report No. 50-321/1980-094.
I C DE CODE SUBCO E COYPONENT CODE SLBC DE SU ODE lo19l lM lB l@ lA l@ l X l@ l V l A l L l V i E l X l@ J@ l Nl@
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9 10 11 12 13 18 19 20 SEQUEN TI A L OCCURRENCE REPORT AEVISION EVENTYEAR REPORT NO.
CODE TYPE NO.
@ "LE A ROu g l218l1l l-l l015l6l [f_j lo 13 l
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECT lVE ACTIONS h liloll The cause of this event has been attributed to oersonnel error.
Root I
li li I l Valve N62-F064A was found to be closed.
Valve N62-F064A was ooened I
ii i7i I and N62-N009A was returned to service.
The unit is now in full I
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compl iance.
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LER No.: 50-321/1981-056 Licensee: Georgia Power Company Facility:
Edwin I. Hatch Docket No. : 50-321
Narrative
Report for LER 50-321/1981-056 While the plant was in start-up, IN62-N009A, Off-gas H2 Analyzer, was found to be inoperative. The event date is unknown, but was reported inoperative on June 10, 1981. Tech Specs Table 2.1.3.h, page 2-7, requires one operable channel.
Redundant H2 Analyzer, IN62-N009B, was operable.
The health Plant operation was not affected as a result of this event.
and safety of the public was not affected.
This is a repetitive event as last reported on Reportable Occurrence Report 50-321/1980-094.
The cause of this event has been attributed to personnel error.
Root Valve, N62-F064A, was found to be closed. Valve N62-F064A was opened and N62-N009A returned to service.
The unit is now in full compliance with the requirements and no further reporting is required.
A generic review revealed no inherent problems.
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Georg a Power Company Post Ott,ce Box e42 Bauley. Georgta 31513 op}.1CIAL Cf ti>1' r 'eonone912 367 778, e
912 537-9444 m
Edwin 1. Hatch Nuclear Plani i. :l COrgia POWCT ttne sourtnwn eucre sywn July 2, 1981 PM-81-575
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PLANT E. I. HATCH Docket No. 50-321
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Licensee Event Report g
T3 United States Nuclear Regulatory Commission 6
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Office of Inspection and Enforcement
%E Region II Suite 3100 101 Marietta Street
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g Atlanta, Georgia 30303 T /I ATTENTION:
Mr. James P. 0'Reilij Pursuant to Section 6.9.1.9.c of Hatch Unit I Technical Specifications, please find attached Reportable Occurrence Report No.50-321/1981-056.
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Plant Manager MM/RTN/mla xc:
J. H. Miller, Jr.
R. J. Kelly W. A. Widner J. T. Beckham, Jr.
C. L. Coggin R. D. Baker Control R00m ff File [4
U. S. NUCLEAR REGULATORY COMMISSION NRC FOFIM 366 17 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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60 61 OOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121 l While the clart was in start-uo.1N62-N009A. O'f-nas H3 Analyzer was l
[ol3} l found to be inoperative.
The event date is unknown, but reported in-I lo l4 l l operative on June 10, 1981.
Tech Specs Table 2.1.3.h reou f res one ooer-I lo Is! l able channel.
Redundant H2 Analyzer., IN62-N0098, was operable. Plant I
lo is ] l operation nor the health and safety of the oublic was not affected by 1
l0l7ll this event.
This is a repetitive event is last reported on Reportable l
loisl l Occurrence Report No. 50-321/1980-094.
I DE CODE SLBCO E COMPONENT CODE SU CODE S
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9 10 11 12 13 la 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION
,, EVENT YEAR REPORT NO.
CODE TYPE NO.
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40 41 42 43 44 47 CAUSE DESCRIPTIO:'i AND CORRECTIVE ACTIONS h lilo1l The cause of this event has been attributed to oersonnel error.
Root I
li liI i Valve N62-F064A was found to be closed.
Valve N62-F064A was oopned I
t iii2i l and J62-N009A was returned to service.
The unit is now in full I
l 1it3l l compl iance.
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% POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION Iil5l d @ l0l0l1l@(_
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[.Aj@lInstrumentTechnicianObservation I
ACTIVITY CO TENT
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PERSONNE L INJURIES NUY8ER
DESCRIPTION
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7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q TYPE
DESCRIPTION
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LER No. :
50-321/1981-056 Licensee: Georgia Power Company Facility:
Edwin I. Hatch Pocket No.:
50-321 Narrative Report for LER 50-321/1981-056 While the plant was in start-up, IN62-N009A, Off-gas H2 Analyzer, was found to be inoperative. The event date is unknown, but was reported inoperative on June 10, 1981.
Tech Specs Table 2.1.3.h, page 2-7, requires one operable channel.
Redundant H2 Analyzer, IN62-N0098, was operable.
Plant operation was not affected as a result of this event.
The health and safety of the public was not affected.
This is a repetitive event as last reported on Reportable Occurrence Report 50-321/1980-094.
The cause of this eveng has been attributed to personnel error.
Root Valve, N62-F064A, wbs Qfbund to be closed.
Valve N62-F064A was opened and N62-N009A returned to service.
The unit is now in full compliance with the requirements and no further reporting is required.
A generic review revealed no inherent problems.
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| 05000366/LER-1981-001-03, /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | /03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris | | | 05000366/LER-1981-001, Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | | | 05000321/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000321/LER-1981-001-01, /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | | | 05000366/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000366/LER-1981-002-03, /03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr | /03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr | | | 05000321/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000321/LER-1981-002-03, /03L-0:on 810101,more than 5 Gpm Leaked Into Drywell W/Reactor at 401 Mwe.Caused by Mechanical Seal Leaking Water from Reactor Recirculation pump,1B31-C001A. Seal Replaced | /03L-0:on 810101,more than 5 Gpm Leaked Into Drywell W/Reactor at 401 Mwe.Caused by Mechanical Seal Leaking Water from Reactor Recirculation pump,1B31-C001A. Seal Replaced | | | 05000366/LER-1981-003-03, /03L-0:on 810223,core Max Fraction of Limiting Power Density Found to Be Greater than Frtp During Startup. Caused by Time Delays for Adjusting Rods,Running Transient Incore Probe Scans & Processing Time for Computer | /03L-0:on 810223,core Max Fraction of Limiting Power Density Found to Be Greater than Frtp During Startup. Caused by Time Delays for Adjusting Rods,Running Transient Incore Probe Scans & Processing Time for Computer | | | 05000321/LER-1981-003-03, /03L-0:on 810130,HPCI Governor Valve Stuck Open. Caused by Lift Rod Being Bent & Galled Due to Interference Between Lift Rod Fork Connector & Valve Lever.Damaged Rod Replaced,Upper Guide Bushing Honed & Fork Modified | /03L-0:on 810130,HPCI Governor Valve Stuck Open. Caused by Lift Rod Being Bent & Galled Due to Interference Between Lift Rod Fork Connector & Valve Lever.Damaged Rod Replaced,Upper Guide Bushing Honed & Fork Modified | | | 05000366/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000321/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000366/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000366/LER-1981-004-03, /03L-0:on 810122,nozzle Loads Found Exceeding Vendor Allowables for Reactor Core Isolation Cooling Steam Turbine During Reanalysis of Piping & Hangers Per IE Bulletin 79-14.Caused by Ae Error in Sys Design | /03L-0:on 810122,nozzle Loads Found Exceeding Vendor Allowables for Reactor Core Isolation Cooling Steam Turbine During Reanalysis of Piping & Hangers Per IE Bulletin 79-14.Caused by Ae Error in Sys Design | | | 05000321/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000321/LER-1981-004-03, /03L-0:on 810106,w/unit in Steady State Power Operation,Qa Audit Showed That Temporary Procedure Change HNP-818 Was Not Approved by Plant Manager within 14 Days of Implementation.Caused by Deletion of Requirement | /03L-0:on 810106,w/unit in Steady State Power Operation,Qa Audit Showed That Temporary Procedure Change HNP-818 Was Not Approved by Plant Manager within 14 Days of Implementation.Caused by Deletion of Requirement | | | 05000366/LER-1981-005-01, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | | | 05000366/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000321/LER-1981-005-03, /03L-0:on 810113,during Steady State Operation, Drywell Temp Recorder IT47-R612 Found to Be Inoperative. Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam | /03L-0:on 810113,during Steady State Operation, Drywell Temp Recorder IT47-R612 Found to Be Inoperative. Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam | | | 05000321/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000366/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000366/LER-1981-006-03, /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | /03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed | | | 05000321/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000321/LER-1981-006-03, /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-007-03, /03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. Personnel Reinstructed | /03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. Personnel Reinstructed | | | 05000366/LER-1981-007-03, /03L-0:on 810126,discovered That on 810124 & 25 Reactor Coolant Sampled from Wrong Sample Line.Caused by Lack of Communication Among Personnel Who Collect & Analyze Reactor Coolant.Personnel Instructed & Coolant Sampled | /03L-0:on 810126,discovered That on 810124 & 25 Reactor Coolant Sampled from Wrong Sample Line.Caused by Lack of Communication Among Personnel Who Collect & Analyze Reactor Coolant.Personnel Instructed & Coolant Sampled | | | 05000366/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-008-03, /03L-0:on 810216,in Normal Operations at 309 Mwt, 1E51-N012A,B,C & D Actuated at 10.2,11.3,11.2 & 10.7 Psig, Respectively.Caused by Switch Setpoint Drift.Barksdale Switches Recalibr | /03L-0:on 810216,in Normal Operations at 309 Mwt, 1E51-N012A,B,C & D Actuated at 10.2,11.3,11.2 & 10.7 Psig, Respectively.Caused by Switch Setpoint Drift.Barksdale Switches Recalibr | | | 05000321/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008-03, /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | | | 05000366/LER-1981-009-03, /03L-0:on 810212,reactor Coolant Not Analyzed Once Per 24-h as Required by Tech Spec.Caused by Reactor Vessel Hydro During Time Period When Next Conductivity Measurement Was to Be Taken | /03L-0:on 810212,reactor Coolant Not Analyzed Once Per 24-h as Required by Tech Spec.Caused by Reactor Vessel Hydro During Time Period When Next Conductivity Measurement Was to Be Taken | | | 05000366/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000321/LER-1981-009-03, /03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments | /03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments | | | 05000321/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000366/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000366/LER-1981-010-03, /03L-0:on 810222,reactor Core Isolation Cooling Auto Flow Controller Did Not Control Turbine Properly While in Auto Position During Quickstart Test.Caused by Loose Ribbon Connector on Flow Control M-4 Station | /03L-0:on 810222,reactor Core Isolation Cooling Auto Flow Controller Did Not Control Turbine Properly While in Auto Position During Quickstart Test.Caused by Loose Ribbon Connector on Flow Control M-4 Station | | | 05000321/LER-1981-010, Forwards LER 81-010/01T-0 | Forwards LER 81-010/01T-0 | | | 05000321/LER-1981-010-01, /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | | | 05000321/LER-1981-011-03, /03L-0:on 810214,liquid Radwaste Sample Tank, WSTB1,discharged Prior to Analysis,Contrary to Ets.Caused by Technician Error in Collecting Unit 2 Radwaste Sample in Prelabeled Unit 1 WSTB-1 Bottle | /03L-0:on 810214,liquid Radwaste Sample Tank, WSTB1,discharged Prior to Analysis,Contrary to Ets.Caused by Technician Error in Collecting Unit 2 Radwaste Sample in Prelabeled Unit 1 WSTB-1 Bottle | | | 05000321/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000366/LER-1981-011-03, /03L-0:on 810204,nonrated Window Discovered in 3-h Rated Fire Wall.Caused by Design,Mfg & Const/Installation Error.Direct Conversion Reactor Study 81-48 Submitted & Fire Watch Established | /03L-0:on 810204,nonrated Window Discovered in 3-h Rated Fire Wall.Caused by Design,Mfg & Const/Installation Error.Direct Conversion Reactor Study 81-48 Submitted & Fire Watch Established | | | 05000366/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000321/LER-1981-012-03, /03L-0:on 810228,turbine Failed to Trip on Overspeed.Caused by Dried Lubrication Around Overspeed Tripping Mechanisms Causing Binding.Mechanism Disassembled, Cleaned,Relubricated & Reassembled | /03L-0:on 810228,turbine Failed to Trip on Overspeed.Caused by Dried Lubrication Around Overspeed Tripping Mechanisms Causing Binding.Mechanism Disassembled, Cleaned,Relubricated & Reassembled | | | 05000321/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000366/LER-1981-012-02, /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | /02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced | | | 05000366/LER-1981-012, Forwards LER 81-012/02L-0 | Forwards LER 81-012/02L-0 | | | 05000366/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000321/LER-1981-013-03, /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | /03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired | |
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