LER-1979-130, Revised 79-130/01T-1:on 791227,clearance Between RCS Hot Leg & Four Large Shims of Pipe Whip Restraints R-4 Determined to Be Insufficient.Caused by Design Error.Pipe Whip Restraints R1 & R4 Modified & R3 Shim Removed |
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EVENT DESCRIPilON AND PROBABLE CONSEQUENCES h [ll 0121 l On 12/21/79 it was discovered there was insufficient clearance between the Reactor l
{ g3J l Coolant System (RCS) hot leg and the four large shims of pipe whip restraints R-4.
On j o l4 l l 12/27/79, it was determined this was in conflict with the reactor supplier's RCS pip-l l o 151 l ing seismic analysis assumptions that there be no contact between RCS hot leg piping j o is 1 Land whip restraints during a seismic event. This became immediately reportable under g
] l o l 71 l T.S. 6.9.1.8.h.
There was no danger to the public or station personnel. These pipe whip restraints do not affect normal operation.
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g Under Facility Change Request 79-441 Supplement 1, pipe whip restraints R1 and R4
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The work was completed by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on 12/29/79.
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-14 DATE OF EVENT: Dec ember 27, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: A conflict between an assumption in the Reactor Coolant System (RCS) piping seismic analysis and six pipe whip restraints
' Conditions Prior to Occurrence: The unit was in Mode 5, with Power (MWT) = 0, and Load (Gross MWE) = 0.
Description of Occurrence: On December 21, 1979, while performing modifications under Facility Change Request 79-441 on RCS hot leg pipe whip restriants R-4, one on each hot leg, it was discovered that the large shims on the north and south side of the restraint could not be moved into their modified position without contacting the hot leg. This condition was reviewed to determine the minimum gap required be-tween these shims and the hot leg. On December 27, 1979, while performing this re-view, it was determine 1 that there was a conflict between the reactor supplier's RCS piping seismic analysis and the design of pipe whip restraints R-4.
The reactor supplier's seismic analysis assumed that during a design basis seismic event that there was unrestrained movement of the RCS pipe. During this review, it was dis-covered that the gaps between the large north-south shims and the RCS piping were not large enough to permit this unrestrained movemea*
This review also revealed the same conflict to exist between the large north th shims of pipe whip restraints R-3 and R-1 and the RCS piping.
All other shims o.
sese restraints are smaller and cict provide adequate gaps for seismic motion. This became immediately reportable under Technical Specification 6.9.1.8.h as a condition which conflicts with an 1
assumption of an accident analysis.
Being in cold shutdown (Mode 5), the unit remained down until corrections were made.
Designation of Apparent Cause of Occurrence: The cause of the occurrence was a design error by the architect / engineer, Bechtel Power Corporation, in that suffi-cient gap had not been provided between the large north-south shims of pipe whip res-traints R-1, R-3 and R-4 and the RCS hot leg to permit unrestrained movement during a seismic event as assumed by the reactor supplier's RCS piping seismic analysis.
Bechtel has reviewed all pipe whip restraints to determine if there are any other instances where large shims (i.e., larger than the other shims on the same restraint) have been used which could produce gaps that would conflict with the assumptions in
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the seismic analysis. This review uncovered no other similar designs.
Based on this j
review, there is no reason to believe that these design errors were a result of any generic deficiency in the original design method.
Anal'ysis of Occurrence: There was no danger to the health'and safety of the public or to station perso'nnel. These pipe whip restraints' arc not required for normal operation.
LER #79-130 i
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P TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-14 PAGE 2
Corrective Action
Under Facility Change Request 79-441 Supplement 1, pipe whip restraints R-1, R-3 and R-4 have been modified so that the gap between the north-l south shims and the hot leg piping is greater than the calculated seismic motion but does not exceed the gap used to verify the whip restraint design.
This was 1
accomplished on restraints R-1 and R-4 by removing the adjustable portion of the shims.
The shims on restraint R-3 were completely removed. There are no other shims on res-l traint R-3.
The gap between the pipe and the close fitting restraint ring of res-i
. traint R-3 was the gap used in the restraint design. All affected whip restraint l-modifications were completed by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on December 29, 1979, prior to the unit l
returning to operation.
Failure Data: There are no previously reported conflicts between the pipe whip restraints and the assumptions of the seismic analysis.
LER #79-130 l
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| 05000346/LER-1979-001-03, /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | | | 05000346/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000346/LER-1979-002-03, /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | | | 05000346/LER-1979-002, Forwards LER 79-002/03L-1 | Forwards LER 79-002/03L-1 | | | 05000346/LER-1979-003-03, /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | | | 05000346/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000346/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000346/LER-1979-004-03, /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | | | 05000346/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000346/LER-1979-005-03, /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | | | 05000346/LER-1979-006-03, /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | | | 05000346/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000346/LER-1979-007-03, /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | | | 05000346/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000346/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000346/LER-1979-008-03, /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | | | 05000346/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000346/LER-1979-009-03, /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | | | 05000346/LER-1979-010-03, /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | | | 05000346/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000346/LER-1979-011-03, /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | | | 05000346/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000346/LER-1979-012-03, /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | | | 05000346/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000346/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000346/LER-1979-013-03, /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | | | 05000346/LER-1979-014-03, /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | | | 05000346/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000346/LER-1979-015-03, /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | | | 05000346/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000346/LER-1979-016-03, /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | | | 05000346/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000346/LER-1979-017-03, /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | | | 05000346/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000346/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000346/LER-1979-018-03, /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | | | 05000346/LER-1979-019-03, /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | | | 05000346/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000346/LER-1979-020-03, /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | | | 05000346/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000346/LER-1979-021-03, /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | | | 05000346/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000346/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000346/LER-1979-022-03, /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | | | 05000346/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000346/LER-1979-023-01, /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | | | 05000346/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000346/LER-1979-024-03, /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | | | 05000346/LER-1979-025-03, /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | | | 05000346/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | |
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