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LER-1981-002, /03L-0:on 810130,three Snubbers Failed to Lock Up as Required by Tech Spec.Caused by Worn Piston Ring Seals & Springs W/Excessive Spring Constants.Snubber Seals,Pistons, Valve Blocks & Weight Springs Replaced |
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| 2891981002R03 - NRC Website |
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Attachmtnt 1 L1L 061
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EVENT DESCRIPT1oN ANo mMo0 ASLE CONSEQUENCE during the refueling interval surveillance y
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I o i 4 I I was a violation of Specification' 4.17.4 and is reportable per 6.9.2.B(2).
There l l c i s i I have been neither seismic events or severe transients to affect the piping nor l
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NARRATIVE
REPOR-Llt 061 TMI-1 LER 81-02/3L-0 l
I.
Current Activities at the Time of Occurrence Functional Testing of hydraulic snubbers in accordance with Surveillance Procedure 1303-9.9 in progress.
Snubb.:- RC-19 failed on January 30, 1981, due to a f ailure to lockup in both tension and compression direction.
Snubber DH-32 failed on February 6,1981, due to a f ailure to lockup in both tension and compression direction. Snubber RC-22 failed on February 20 4
1981, due to a failure to lockup in both tension and compression direction.
II.
Leading Circumstances While performing testing of hydraulic snubbers in accordance with SP1303-9.9, RC-19, DH-32 and RC-22 f ailed to lockup as required.
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III. Description
The Unit.has been in extended cold shutdown conditions since April, 1979.
The snubbers failed during refueling interval functional testing which was being performed to satisfy Technical Specification 4.17.4 require-ments. Since the failed snubbers were not functional tested rabsequent to the March,1979 heatup, the exact time of the failure is unknown.
Therefore, this item is considered reportable under Technical Spec-ification 6.9.2.B.(2).
IV.
Resultant Events Since there has been no earthquake or severe transient which would have caused unrestrained pipe motion under dynamic loading during the March, 1979 heatup or subsequent to then, there are no significant occurrences which l
have taken place as a result of these snubber f ailures.
j V.
Previous Events of a Similar Nature During 1979, snubber RC-19 also f ailed to lockup af ter it was visually discovered to have a broken sight glass. Snubber NSE-151 f ailed to lockup i
4 in July, 1980. LER 80-14/3L was submitted describing that occurrence.
VI.
Root Cause RC-19 failure is attributed to worn piston rirgs seals in the snubber cylinder. DH-32 f ailure is attributed to springs in the snubber valve r
block having too high a spring constant to allow lockup of the snubber.
RC-22 failure is attributed to worn piston *ings seals within the snubber cylinder.
VII.
Imnediate Corrective Action RC-19 snubber was rebuilt using spare replacement parts and new seals.
The springs in valve block were also replaced with lighter weight springs to obtain activation velocities within the specified range for compression and tension lockup.
Springs in DH-32 valve block were replaced with lighter a
weight springs.
s Narrative Report LER 81-02/3L Page 2 i
VII.
I= mediate Corrective Action Cc.t'd RC-22 was completely overhauled with new piston 'O'-ring seals, new valve i
block and lighter valve block springs.
All three snubbers were retested satisfactorily and reinstalled in the plant. Additional snubbers will be tested to comply with Technical Specification 4.17.4 requirements.
VIII. Lone Ter= Corrective Action j
Since all three snubbers were of the sane manuf acturer, all saf ety-related snubbers of that manuf acturer are scheduled for removal and functional testing to assure their operability for plant startup.
IX.
Co=conent Failure Data Basic Engineers - BE 411 Hydraulic Shock and Sway Suppressor - 1h" x 5" stroke.
Mark No. RC-19 Basic Engineers - BE 411 Hydraulic Shock and Sway Suppressor - 3/4" x 5" stroke.
Mark No. DH-32 Basic Engineers - BE-410 Hydraulic Shock and Sway Suppressor - 3/4" x 5" stroke.
Mark No. RC-22 I
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| 05000289/LER-1981-001, Forwards LER 81-001/03L-1.Detailed Event Analysis Encl | Forwards LER 81-001/03L-1.Detailed Event Analysis Encl | | | 05000320/LER-1981-001, Has Been Cancelled | Has Been Cancelled | | | 05000289/LER-1981-001-03, /03L-1:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17 During Limited Plant Heatup.Caused by Flange Socket Fillet Weld Failure Due to fabrication-induced Crack in Root of Weld | /03L-1:on 810117,two Leaks Found in 1-inch Bypass Around MU-V17 During Limited Plant Heatup.Caused by Flange Socket Fillet Weld Failure Due to fabrication-induced Crack in Root of Weld | | | 05000289/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000320/LER-1981-002-01, /01L-0:on 810126,emergency Diesel Generator B Determined Inoperable on 810119.Caused by Auxiliary Operator Not Completing Switching Order.No Corrective Action.Operator Counseled | /01L-0:on 810126,emergency Diesel Generator B Determined Inoperable on 810119.Caused by Auxiliary Operator Not Completing Switching Order.No Corrective Action.Operator Counseled | | | 05000320/LER-1981-002, Forwards LER 81-002/01L-0 | Forwards LER 81-002/01L-0 | | | 05000289/LER-1981-002-03, /03L-0:on 810130,three Snubbers Failed to Lock Up as Required by Tech Spec.Caused by Worn Piston Ring Seals & Springs W/Excessive Spring Constants.Snubber Seals,Pistons, Valve Blocks & Weight Springs Replaced | /03L-0:on 810130,three Snubbers Failed to Lock Up as Required by Tech Spec.Caused by Worn Piston Ring Seals & Springs W/Excessive Spring Constants.Snubber Seals,Pistons, Valve Blocks & Weight Springs Replaced | | | 05000320/LER-1981-003-03, /03L-0:on 810202,while Performing Surveillance 4333-R2,deluge Valve FS-V-426A Failed to Operate Properly. Apparently Caused by Malfunction of Solenoid Operator, Arresting Automatic Release of Hydraulic Lock | /03L-0:on 810202,while Performing Surveillance 4333-R2,deluge Valve FS-V-426A Failed to Operate Properly. Apparently Caused by Malfunction of Solenoid Operator, Arresting Automatic Release of Hydraulic Lock | | | 05000289/LER-1981-003-03, /03L-0:on 810210,new Penetration in Fire Wall Between Engineered Safeguards Actuation Sys,Fire Area CB-3C & Relay Room,Fire Area CB-3D,found Necessary for New Cable Routing for Mods on Containment Isolation RM-5C | /03L-0:on 810210,new Penetration in Fire Wall Between Engineered Safeguards Actuation Sys,Fire Area CB-3C & Relay Room,Fire Area CB-3D,found Necessary for New Cable Routing for Mods on Containment Isolation RM-5C | | | 05000320/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000289/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000320/LER-1981-004-03, /03L-0:on 810204,emergency Diesel Generator, DF-X-1B,failed to Start.Caused by Low Diesel Ambient Temp. Temp Maintained by Periodic Starting Until Pump Motor Repair on 810302 | /03L-0:on 810204,emergency Diesel Generator, DF-X-1B,failed to Start.Caused by Low Diesel Ambient Temp. Temp Maintained by Periodic Starting Until Pump Motor Repair on 810302 | | | 05000320/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000289/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000289/LER-1981-004-03, /03L-0:on 810324,during Refueling Interval Functional Testing of Hydraulic Snubbers,Snubber RC-21/MUE-43 Discovered W/Shipping Plug Installed in Fluid Reservoir Vent Port.Caused by Procedure Violation | /03L-0:on 810324,during Refueling Interval Functional Testing of Hydraulic Snubbers,Snubber RC-21/MUE-43 Discovered W/Shipping Plug Installed in Fluid Reservoir Vent Port.Caused by Procedure Violation | | | 05000289/LER-1981-005-99, /99X-0:on 810122,cumulative Reactor Utilization Factor Was Determined Not to Meet Newly Amended Tech Spec. Caused by Amending Tech Specs W/O Verifying Record.Tech Spec Will Be Changed | /99X-0:on 810122,cumulative Reactor Utilization Factor Was Determined Not to Meet Newly Amended Tech Spec. Caused by Amending Tech Specs W/O Verifying Record.Tech Spec Will Be Changed | | | 05000289/LER-1981-005, Forwards LER 81-005/99X-0 | Forwards LER 81-005/99X-0 | | | 05000320/LER-1981-005-01, /01L-0:on 810207,incore Thermocouple H-9 Exhibited Erratic Behavior.Cause Unknown.Thermocouple Being Monitored to Determine Trend & long-term Safety Implications | /01L-0:on 810207,incore Thermocouple H-9 Exhibited Erratic Behavior.Cause Unknown.Thermocouple Being Monitored to Determine Trend & long-term Safety Implications | | | 05000320/LER-1981-005, Forwards LER 81-005/01L-0 | Forwards LER 81-005/01L-0 | | | 05000289/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000289/LER-1981-006-03, /03L-0:on 810507,corrosion on Diesel Fire Pump Battery Terminals Noted.Caused by Failure to Include Surveillance in Computer Tracking Sys.Surveillance Entry Into Computer Data Base Verified | /03L-0:on 810507,corrosion on Diesel Fire Pump Battery Terminals Noted.Caused by Failure to Include Surveillance in Computer Tracking Sys.Surveillance Entry Into Computer Data Base Verified | | | 05000320/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000320/LER-1981-006-03, /03L-0:on 810226,A Emergency Diesel Generator DF-X-1A Tripped Approx 15 to 20-s After Starting.Cause Unknown.Brush Recorders Are Being Installed to Monitor Several Components in Starting Circuitry | /03L-0:on 810226,A Emergency Diesel Generator DF-X-1A Tripped Approx 15 to 20-s After Starting.Cause Unknown.Brush Recorders Are Being Installed to Monitor Several Components in Starting Circuitry | | | 05000320/LER-1981-007-01, /01L-0:on 810311,EPICOR-II Bldg Radiation Monitor Removed from Svc for Maint W/O Initiating Air Grab Samples Per Ets.Caused by Insufficient Communication Between Personnel & Foreman | /01L-0:on 810311,EPICOR-II Bldg Radiation Monitor Removed from Svc for Maint W/O Initiating Air Grab Samples Per Ets.Caused by Insufficient Communication Between Personnel & Foreman | | | 05000289/LER-1981-007-99, /99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified | /99X-0:on 810702,pipe Supports Found Located or Oriented Improperly When Installed Per IE Bulletin 79-02 & 79-14 Insp Results.Caused by Inadequate Insp Prior to Operation.Supports Are Being Modified | | | 05000289/LER-1981-007, Forwards LER 81-007/99X-0 | Forwards LER 81-007/99X-0 | | | 05000320/LER-1981-007, Forwards LER 81-007/01L-0 | Forwards LER 81-007/01L-0 | | | 05000289/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000289/LER-1981-008-03, /03L-0:on 810907,reactor Bldg Access Doors Resilient Seals Discovered Not Being Tested at Frequency Required by Tech Spec.Caused by Personnel Error Possibly Due to Nonprecise Procedural Guidance.Access Doors Tested | /03L-0:on 810907,reactor Bldg Access Doors Resilient Seals Discovered Not Being Tested at Frequency Required by Tech Spec.Caused by Personnel Error Possibly Due to Nonprecise Procedural Guidance.Access Doors Tested | | | 05000320/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000320/LER-1981-008-03, /03L-0:on 810416,while Unit 1 Was Flushing Fire Sys Loop,Unit 2 Diesel Driven Fire Pump Received Automatic Start Signal But Failed to Start.Possibly Caused by Failed Battery Bank A.Diesel Was Switched to B Bank | /03L-0:on 810416,while Unit 1 Was Flushing Fire Sys Loop,Unit 2 Diesel Driven Fire Pump Received Automatic Start Signal But Failed to Start.Possibly Caused by Failed Battery Bank A.Diesel Was Switched to B Bank | | | 05000289/LER-1981-009, Forwards LER 81-009/01T-0 | Forwards LER 81-009/01T-0 | | | 05000320/LER-1981-009, Has Been Canceled | Has Been Canceled | | | 05000289/LER-1981-009-01, /01T-0:on 810117,emergency Diesel Generator Feeder Breaker Logic Anomaly Discovered Which Could Result in Damaged Motor or Generator End Turns & Excessive Voltage Dip on Diesel Generator.Caused by Design Error | /01T-0:on 810117,emergency Diesel Generator Feeder Breaker Logic Anomaly Discovered Which Could Result in Damaged Motor or Generator End Turns & Excessive Voltage Dip on Diesel Generator.Caused by Design Error | | | 05000320/LER-1981-010, Forwards LER 81-010/01L-0 | Forwards LER 81-010/01L-0 | | | 05000289/LER-1981-010, Forwards LER 81-010/03L-0.Detailed Event Analysis Encl | Forwards LER 81-010/03L-0.Detailed Event Analysis Encl | | | 05000320/LER-1981-010-01, /01L-0:on 810420,during Normal Operations,Shift & Daily Check Logsheet Listed Seven Instruments Receiving Daily Rather than Per Shift Checks as Required.Caused by Errors in Logsheet.Procedures Logsheet Revised | /01L-0:on 810420,during Normal Operations,Shift & Daily Check Logsheet Listed Seven Instruments Receiving Daily Rather than Per Shift Checks as Required.Caused by Errors in Logsheet.Procedures Logsheet Revised | | | 05000289/LER-1981-010-03, QC Audit Showed One of 21 Reactor Bldg Prestressing Tendons Inspected During 1980 Surveillance Had Low Liftoff Force.Caused by Use of Incorrect Calibr Data.Procedure Being Rewritten | QC Audit Showed One of 21 Reactor Bldg Prestressing Tendons Inspected During 1980 Surveillance Had Low Liftoff Force.Caused by Use of Incorrect Calibr Data.Procedure Being Rewritten | | | 05000289/LER-1981-011, Updated LER 81-011/01T-1:on 811019,determined That Catwalk Structure,Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Did Not Meet Seismic Criteria. Caused by Ae Failure to Perform Calculations | Updated LER 81-011/01T-1:on 811019,determined That Catwalk Structure,Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Did Not Meet Seismic Criteria. Caused by Ae Failure to Perform Calculations | | | 05000289/LER-1981-011-01, /01L-O:on 811019,catwall Structure Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Determined Inadequately Designed for Seismic Loads. Caused by Lack of Seismic Design Calculations by Ae | /01L-O:on 811019,catwall Structure Used to Support Cable Trays,Conduit & Terminal Blocks for Control Consoles Determined Inadequately Designed for Seismic Loads. Caused by Lack of Seismic Design Calculations by Ae | | | 05000320/LER-1981-011-01, /01P-0:on 810423,nuclear Svcs River Water Pump NR-P-1A Was Declared Inoperable.Pump Cannot Be Repaired within Time Allowed by Tech Spec Due to Unavailability of Spare Parts.Details to Follow | /01P-0:on 810423,nuclear Svcs River Water Pump NR-P-1A Was Declared Inoperable.Pump Cannot Be Repaired within Time Allowed by Tech Spec Due to Unavailability of Spare Parts.Details to Follow | | | 05000289/LER-1981-012-04, /04L-0:on 811116,ETS 2.2.1.a,limiting Condition for Riverwater Chlorination,Was Exceeded.Caused by Malfunctioning Timing Device.Faulty Timer Repaired.Tech Spec Change Request 100A Allows Condition to Equal NPDES Permit | /04L-0:on 811116,ETS 2.2.1.a,limiting Condition for Riverwater Chlorination,Was Exceeded.Caused by Malfunctioning Timing Device.Faulty Timer Repaired.Tech Spec Change Request 100A Allows Condition to Equal NPDES Permit | | | 05000320/LER-1981-012-03, /03L-0:on 810422,during Followup Test,Emergency Diesel Generator a Was Started,But Failed to Develop Output Voltage.Caused by Failed Latching Mechanism in K-1 Relay,Due to Corrosion of Contacts.Relay Was Replaced | /03L-0:on 810422,during Followup Test,Emergency Diesel Generator a Was Started,But Failed to Develop Output Voltage.Caused by Failed Latching Mechanism in K-1 Relay,Due to Corrosion of Contacts.Relay Was Replaced | | | 05000320/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000289/LER-1981-012, Forwards LER 81-012/04L-0 | Forwards LER 81-012/04L-0 | | | 05000289/LER-1981-013-01, /01X-1:on 811125,bubble Leakage Test Indicated Leaking Tubes in once-through Steam Generators (OTSG) a & B. Caused by Inadvertent Introduction of Sulfur Into Rcs. Chemical Agent Removed & OTSGs Repaired | /01X-1:on 811125,bubble Leakage Test Indicated Leaking Tubes in once-through Steam Generators (OTSG) a & B. Caused by Inadvertent Introduction of Sulfur Into Rcs. Chemical Agent Removed & OTSGs Repaired | | | 05000289/LER-1981-013, Forwards LER 81-013/01T-0 Re Leaking Found in Steam Generators.Event Reportable Per Tech Spec 6.9.2.A(3). Supporting Documentation Encl | Forwards LER 81-013/01T-0 Re Leaking Found in Steam Generators.Event Reportable Per Tech Spec 6.9.2.A(3). Supporting Documentation Encl | | | 05000320/LER-1981-014-03, /03L-0:on 810507,corrosion Noted on Battery Terminals of Diesel Fire Pump.Caused by Failure to Perform or Reschedule Surveillance Since Sept 1977 Due to Error in Computer Entry | /03L-0:on 810507,corrosion Noted on Battery Terminals of Diesel Fire Pump.Caused by Failure to Perform or Reschedule Surveillance Since Sept 1977 Due to Error in Computer Entry | | | 05000289/LER-1981-014-01, /01T-0:on 811223,during IE Bulletin 79-02/14 Insps of Pipe Supports,Nine Structural Interfacing Areas Were Identified as-built in Nonconformance to Original Design Areas in Final Stages of Mod.Reanalysis Initiated | /01T-0:on 811223,during IE Bulletin 79-02/14 Insps of Pipe Supports,Nine Structural Interfacing Areas Were Identified as-built in Nonconformance to Original Design Areas in Final Stages of Mod.Reanalysis Initiated | | | 05000320/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | |
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