LER-1978-092, /01T-0 on 781219:final Stress Rept Shows That 15 Pipe Supports Were Not Installed or Configured as Assumed in Stress Analysis.Caused by Field Revision During Const.Plant Mods Have Been Issued |
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LICENSEE EVENT REPORT CONTROL BLOCC l l
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8 60 61 DOCK E T NUVBE R 68 63 EVENT DATE 74
?S REPORT OATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o
2 10n December 19, 1978, we were informed by the plant architect-engineer that the fin,1 l l stress report review for Brunswick Plant has revealed that approximately 15 pipe sup-1 fo 3
l ports were not installed or configured as assumed in the st.ress analysis and that the 1 o
4 I actual stresses in the as-built conditions are above the normal stresses allowed by j o
s Icode. The stresses are, however, below the stresses allowed by the code under faulted I io o
l conditions (including design basis carthquake), and the lines would be operable nnd l
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o a t intact during these faulted conditions.
(A list of deficiencies is attached).
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CAUSE
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VALVE CODE CODE SUBCCDE COYPONENT CODE SUSCODE SUSCODE l S l F l@ lB l@ lA l@lS l Ul Pl 0 l Rl T l@ lB l@ lZ l@
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9 10 11 12 13 t ti 13 20 SEQUENTI AL OCCURRENCE REFORT REVISION y
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CODE TYPE NC.
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_ 21 22 23 24 26 27 23 29 3J 31 32 ACTION FUTURE EFFECT SHUTDOWN ATT ACHM E N T N P R D-4 PRiVE COMP.
COVPONENT TAKEN ACTION ON PL ANT METHOD HOURS SUBMITTED FORM bub.
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40 41 42 43 44 47 CAUSE oESCRIPTION AND CORRECTIVE ACTIONS l During construction a number of pipe supports were field revised and incorporated i
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i l into the plant design through A/E approved field memorandums. A final stress report l 7
j review by the A/E determined that a number of these changes were unacceptable in theiy l as-built condition.
Plant Modifications have been issued to correct all the pipe l
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NPOWER OTHER$7ATUS ISCO HY DISCOVERY DESCRIPTION lE g l0 l6 l0 lg FA l
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ACTIVITY CONTENT RELEASED OF RE LE ASE AYOUNT OF ACTivlTY LOCATION CF RELE ASE 1 6 lZ @ W@l NA l
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NAYE OF PREPARER
LER COYrINUATION -- ROJ 1-78-092
' Facility: BSEP Unit #1 Event Date 12-19-78 Cause Descriotion and Corrective Actions (cont) completed or, if they have not, the maximum calculated stress for the present unmodified condition (including scismic loads) does not exceed the allowable stress for a faulted condition as defined in Section III of the ASME Code. Thus, the piping will not fail structurally under worst case conditions.
The A/E was requested to review the Unit No. 2 final stress report, where one additional deficiency was found. All modifications will be completed when materials are available.
0 ATTACIDENT (1)
Pipe Support Deficiencies - As Identified By A/E Unit System Line Size Applicable P/M Status & Comments 1
CAC 3/4"78-300 Approved modification sent to PPCD 12/21/78 for installation.
Max. calculated stress in existing condition is 35308 psi which would not fail.
1 RCIC 1"78-300 Approved modification sent to PPCD 12/21/78 for installation.
Failure of the line would not make RCIC inoperable.
1 Se rvice 6"78-300 Approved mod. sent to PPCD. Max Water calculated stress in existing condition 26,980 psi would not fail.
2 Se rvico 6"78-301 Based on this calc. the RHR room coolers (1B & 2B) have been placed back into service.
1 RHR 4"78-300 Approved mod. sent to PPCD.
Max calc. stress in existing condition is 33,392 psi and would not fail.
1 RHR 3/4" & 1"78-299 Comolete 1
RHR 1",1",& 3/4"78-299 Comolete 1
RHR 1"78-299 Comolete 1
RHR 1",1", & 3/4"78-299 Complete
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| 05000325/LER-1978-015, Forwards LER 78-015/03L-0 | Forwards LER 78-015/03L-0 | | | 05000325/LER-1978-015-03, /03L-0 on 780205:during Reactor Recirculation Pump Discharge Valve Cycle Test,Valve B32-F031A Failed in Closed Position Requiring Pump a to Be Secured.Caused by Stuck 42 Auxiliary Contactor.Contractor Realigned | /03L-0 on 780205:during Reactor Recirculation Pump Discharge Valve Cycle Test,Valve B32-F031A Failed in Closed Position Requiring Pump a to Be Secured.Caused by Stuck 42 Auxiliary Contactor.Contractor Realigned | | | 05000325/LER-1978-039-03, /03L-0 on 780412:during Quarterly HPCI Pump Flow Test,Hpci Turbine Control Valve Was Inoperable.Caused by Corrosion Inside Electro/Mechanical/Hydraulic Actuator Preventing Pilot Valve Plunger from Operating | /03L-0 on 780412:during Quarterly HPCI Pump Flow Test,Hpci Turbine Control Valve Was Inoperable.Caused by Corrosion Inside Electro/Mechanical/Hydraulic Actuator Preventing Pilot Valve Plunger from Operating | | | 05000325/LER-1978-039, Forwards LER 78-039/03L-0 | Forwards LER 78-039/03L-0 | | | 05000324/LER-1978-058, Suppl to LER 78-058/03L-1:on 780630,while Performing Penetrant Test 2.1.26PC,I&C Technician Found Pressure Switch B21-PS-N015B Out of Calibr.Caused by Instrument Drift.Switch Recalibr.During Future Outage,Switch Will Be Replace | Suppl to LER 78-058/03L-1:on 780630,while Performing Penetrant Test 2.1.26PC,I&C Technician Found Pressure Switch B21-PS-N015B Out of Calibr.Caused by Instrument Drift.Switch Recalibr.During Future Outage,Switch Will Be Replaced | | | 05000324/LER-1978-059-03, /03L-0 on 780904:RCIC Isolation Channel a Tripped Momentarily,Causing RCIC Sys to Be Inoper,Due to Defective RX-2 Relay | /03L-0 on 780904:RCIC Isolation Channel a Tripped Momentarily,Causing RCIC Sys to Be Inoper,Due to Defective RX-2 Relay | | | 05000324/LER-1978-059, Forwards LER 78-059/03L-0 | Forwards LER 78-059/03L-0 | | | 05000324/LER-1978-064, Forwards LER 78-064/03L-1 | Forwards LER 78-064/03L-1 | | | 05000324/LER-1978-064-03, /03L-1 on 780820:during Testing 3 Hydraulic Snubbers Found Inoperable.Snubber E11-95SS20 Was Low on fluid,G41-22SS85 Was Mechanically Disconnected & E11-37SS95 Had Cracked Support.Each Was Repaired or Replaced | /03L-1 on 780820:during Testing 3 Hydraulic Snubbers Found Inoperable.Snubber E11-95SS20 Was Low on fluid,G41-22SS85 Was Mechanically Disconnected & E11-37SS95 Had Cracked Support.Each Was Repaired or Replaced | | | 05000324/LER-1978-066, Forwards LER 78-066/03L-0 | Forwards LER 78-066/03L-0 | | | 05000324/LER-1978-066-03, /03L-0 on 780904:rod Block Monitor B Inoperative Trip Came on & Stayed on for 1/4 of the Control Rod Selection Matrix.Caused by Failed Integrated Circuit in Rod Block Monitor self-test Circuitry | /03L-0 on 780904:rod Block Monitor B Inoperative Trip Came on & Stayed on for 1/4 of the Control Rod Selection Matrix.Caused by Failed Integrated Circuit in Rod Block Monitor self-test Circuitry | | | 05000324/LER-1978-068, Forwards LER 78-068/03L-0 | Forwards LER 78-068/03L-0 | | | 05000324/LER-1978-068-03, /03L-0:on 780912,during LPCI Pump Discharge Pressure Interlock Channel Functional Test,Pressure Switches E11-PS-N016B & E11-PS-N020D Failed to Actuate at 115 Psig. Caused by Corrosion Buildup in Switch Plungers | /03L-0:on 780912,during LPCI Pump Discharge Pressure Interlock Channel Functional Test,Pressure Switches E11-PS-N016B & E11-PS-N020D Failed to Actuate at 115 Psig. Caused by Corrosion Buildup in Switch Plungers | | | 05000324/LER-1978-069, Forwards LER 78-069/03L-0 | Forwards LER 78-069/03L-0 | | | 05000325/LER-1978-069, Forwards LER 78-069/03L-1 | Forwards LER 78-069/03L-1 | | | 05000325/LER-1978-069-03, Ler 78-069/03L-1 on 780716:outboard Main Steamline Drain Isolation Valve B21-F019 Would Not Operate.Caused by Motor Brushes Not Making Proper Contact W/Commutator | Ler 78-069/03L-1 on 780716:outboard Main Steamline Drain Isolation Valve B21-F019 Would Not Operate.Caused by Motor Brushes Not Making Proper Contact W/Commutator | | | 05000324/LER-1978-069-03, /03L-0:on 780912,fire Alarms Received But Would Not Reset.Fire Detection Instrumentation Inoperable.Caused by Smoke & Dust Resulting from Welding & Operation of Jackhammer.Fire Detectors Cleaned & Repaired | /03L-0:on 780912,fire Alarms Received But Would Not Reset.Fire Detection Instrumentation Inoperable.Caused by Smoke & Dust Resulting from Welding & Operation of Jackhammer.Fire Detectors Cleaned & Repaired | | | 05000324/LER-1978-070-03, /03L-0:on 780923,reactor Coolant Conductivity Exceeded Tech Spec Requirements.Caused by Restarting RWCU Filter Pump After Pump Tripped,Resulting in Resin Injected Into Reactor Coolant.Rwcu Procedure Will Be Revised | /03L-0:on 780923,reactor Coolant Conductivity Exceeded Tech Spec Requirements.Caused by Restarting RWCU Filter Pump After Pump Tripped,Resulting in Resin Injected Into Reactor Coolant.Rwcu Procedure Will Be Revised | | | 05000324/LER-1978-070, Forwards LER 78-070/03L-0 | Forwards LER 78-070/03L-0 | | | 05000324/LER-1978-071-03, /03L-0 on 780924:during RCIC Sys Component Test, Found Throttle Valve E51-v8 in Closed Position.Cause Known | /03L-0 on 780924:during RCIC Sys Component Test, Found Throttle Valve E51-v8 in Closed Position.Cause Known | | | 05000324/LER-1978-071, Forwards LER 78-071/03L-0 | Forwards LER 78-071/03L-0 | | | 05000325/LER-1978-071-03, /03L-0 on 780905:during Periodic Test,Radiat Monitor D12-RM-NO10B HI-HI Trip Point Drifted to Higher than Permitted Level.Monitor Recalibrated.Drift Appears to Be Isolated Incident;No Further Action Taken | /03L-0 on 780905:during Periodic Test,Radiat Monitor D12-RM-NO10B HI-HI Trip Point Drifted to Higher than Permitted Level.Monitor Recalibrated.Drift Appears to Be Isolated Incident;No Further Action Taken | | | 05000325/LER-1978-071, Forwards LER 78-071/03L-0 | Forwards LER 78-071/03L-0 | | | 05000324/LER-1978-072-03, /03L-0 on 781101:rod Block Monitor(Rbm) Channel a Was Found Out of Calibr During Testing Due to Setpoint Drift.Calibr Frequency Will Be Increased from Once to Twice Per Year | /03L-0 on 781101:rod Block Monitor(Rbm) Channel a Was Found Out of Calibr During Testing Due to Setpoint Drift.Calibr Frequency Will Be Increased from Once to Twice Per Year | | | 05000324/LER-1978-072, Forwards LER 78-072/03L-0 | Forwards LER 78-072/03L-0 | | | 05000325/LER-1978-072, Forwards LER 78-072/03L-0 | Forwards LER 78-072/03L-0 | | | 05000325/LER-1978-072-03, /03L-0 on 780911:Snubber SW-142SS164 Found Inoperable During Periodic Test.Caused by Seal Degradation & Resulting Loss of Fluid | /03L-0 on 780911:Snubber SW-142SS164 Found Inoperable During Periodic Test.Caused by Seal Degradation & Resulting Loss of Fluid | | | 05000324/LER-1978-073-03, /03L-0:on 780927,condensate deep-bed Demineralizer Conductivity Recorder Found Inoperable During Shift Turnover Insp.Caused by Turning Off Transmitter Due to Mislabeling of on-off Switch Positions | /03L-0:on 780927,condensate deep-bed Demineralizer Conductivity Recorder Found Inoperable During Shift Turnover Insp.Caused by Turning Off Transmitter Due to Mislabeling of on-off Switch Positions | | | 05000324/LER-1978-073, Forwards LER 78-073/03L-0 | Forwards LER 78-073/03L-0 | | | 05000325/LER-1978-074, Forwards LER 78-074/03L-0 | Forwards LER 78-074/03L-0 | | | 05000325/LER-1978-074-03, /03L-0 on 780911:during Monthly 1 Diesel Generator Load Test,It Was Found That 1 Cylinder Was Not Firing,Due to Faulty Fuel Pump | /03L-0 on 780911:during Monthly 1 Diesel Generator Load Test,It Was Found That 1 Cylinder Was Not Firing,Due to Faulty Fuel Pump | | | 05000324/LER-1978-074-03, /03L-0 on 781112:reactor Steam Dome High Pressure Switch B32-PS-N018B Did Not Reset & Would Not Allow RHR Valve E11-F008 to Open for Shutdown Cooling at Reactor Pressure of 102psig.Caused by Sticking micro-switch | /03L-0 on 781112:reactor Steam Dome High Pressure Switch B32-PS-N018B Did Not Reset & Would Not Allow RHR Valve E11-F008 to Open for Shutdown Cooling at Reactor Pressure of 102psig.Caused by Sticking micro-switch | | | 05000324/LER-1978-074, Forwards LER 78-074/03l-0 | Forwards LER 78-074/03l-0 | | | 05000325/LER-1978-075, Forwards LER 78-075/03L-0 | Forwards LER 78-075/03L-0 | | | 05000324/LER-1978-075-03, /03L-0 on 781122:HPCI & RCIC Component Tests Were Overlooked Because Rescheduling Technique Provided No Clear Indication of Test Due Dates.Responsible Technician Reinstructed & Admin Operating Instruction AOI-5 Rev | /03L-0 on 781122:HPCI & RCIC Component Tests Were Overlooked Because Rescheduling Technique Provided No Clear Indication of Test Due Dates.Responsible Technician Reinstructed & Admin Operating Instruction AOI-5 Rev | | | 05000324/LER-1978-075, Forwards LER 78-075/03L-0 | Forwards LER 78-075/03L-0 | | | 05000325/LER-1978-075-03, /03L-0 on 781004:pressure Switch E11-PS-NO16B Failed During Periods Plci Pump Discharges ADS Permissive Test,Due to Corrosion Buildup on Plunger of Switch | /03L-0 on 781004:pressure Switch E11-PS-NO16B Failed During Periods Plci Pump Discharges ADS Permissive Test,Due to Corrosion Buildup on Plunger of Switch | | | 05000324/LER-1978-076, Forwards LER 78-076/03L-0 | Forwards LER 78-076/03L-0 | | | 05000324/LER-1978-076-03, /03L-0 on 781202:during Routine Check Noted That Recorder for Chloride Intrusion Monitor Channel CO-CIS-3075- 1 Was Not Indicating.Cause Not Determined at This Time,Will Be Investigated During Next Condensate Sys Outage | /03L-0 on 781202:during Routine Check Noted That Recorder for Chloride Intrusion Monitor Channel CO-CIS-3075- 1 Was Not Indicating.Cause Not Determined at This Time,Will Be Investigated During Next Condensate Sys Outage | | | 05000325/LER-1978-076-03, /03L-0 on 781011:torus Level Dropped Below Tech Spec Minimum While Water from Torus Was Being Pumped,Via Rgr to Radwaste in Efforts to Reduce Torus Water Level. Caused by Operator Being Distracted | /03L-0 on 781011:torus Level Dropped Below Tech Spec Minimum While Water from Torus Was Being Pumped,Via Rgr to Radwaste in Efforts to Reduce Torus Water Level. Caused by Operator Being Distracted | | | 05000325/LER-1978-076, Forwards LER 78-076/03L-0 | Forwards LER 78-076/03L-0 | | | 05000324/LER-1978-077, Forwards LER 78-077/03L-0 | Forwards LER 78-077/03L-0 | | | 05000325/LER-1978-077-03, /03L-0 on 781006:condensate Storage Tank Level Switch E41-LS-N003 Found Out of Calibration During Periodic Condensate Storage Tank Low Level Channel.Caused by Instru Drift | /03L-0 on 781006:condensate Storage Tank Level Switch E41-LS-N003 Found Out of Calibration During Periodic Condensate Storage Tank Low Level Channel.Caused by Instru Drift | | | 05000325/LER-1978-077, Forwards LER 78-077/03L-0 | Forwards LER 78-077/03L-0 | | | 05000324/LER-1978-077-03, /03L-0 on 781215:during test,E41-DPIS-N005 Failed to Operate.Caused by Inoperable Relay Due to Faulty Maintenance Work;Relay Wire Was Left Unterminated | /03L-0 on 781215:during test,E41-DPIS-N005 Failed to Operate.Caused by Inoperable Relay Due to Faulty Maintenance Work;Relay Wire Was Left Unterminated | | | 05000325/LER-1978-078, Forwards LER 78-078/03L-0 | Forwards LER 78-078/03L-0 | | | 05000324/LER-1978-078, Forwards LER 78-078/03L-0 | Forwards LER 78-078/03L-0 | | | 05000324/LER-1978-078-03, /03L-0 on 781204:snubber Piston Shaft on Snubber 2SW-174SS174 Was Found Unscrewed from Rod Eye,Making Snubber Inoperable.No Cause Could Be Discerned | /03L-0 on 781204:snubber Piston Shaft on Snubber 2SW-174SS174 Was Found Unscrewed from Rod Eye,Making Snubber Inoperable.No Cause Could Be Discerned | | | 05000325/LER-1978-078-03, /03L-0 on 781105:Control Oper Received Control Rod Drift Alarm for Rod 10-31.When Rod Position Display Was Selected,A False 3 Was Superimposed on Actual Rod Position Due to Aground on the Rpls Probe | /03L-0 on 781105:Control Oper Received Control Rod Drift Alarm for Rod 10-31.When Rod Position Display Was Selected,A False 3 Was Superimposed on Actual Rod Position Due to Aground on the Rpls Probe | | | 05000324/LER-1978-079-03, /03L-0 on 781017:reactor Bldg Radiat Exhaust Monitor D12-RM-N010B Failed Safe Causing Reactor Bldg Vent to Isolate,Due to Defective Transistor 2N1711 on 24V Pwr Supply | /03L-0 on 781017:reactor Bldg Radiat Exhaust Monitor D12-RM-N010B Failed Safe Causing Reactor Bldg Vent to Isolate,Due to Defective Transistor 2N1711 on 24V Pwr Supply | |
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