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LER-1979-039, LER-039/01T-0 on 790523:during Shutdown,One Feedwater Check Valve & Three RHR Pump Suction Valves Deemed to Have Excessive Leak Rates.Caused by Change to ASME Criteria. ASME Criteria Reviewed & Found Too Strigent |
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| 3661979039R01 - NRC Website |
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4 63 61 D~.,,CK E T ALMB ER tid C3 EVEP4T QATE 14 lb (4kPORT O ATE SJ EVENT DESCntPTION AriO PRC9ABLE CONSEQUENCE *, h T D l On flay 23, 1979, while shutdown for anchor bolt insocction and recair, it was discov-l Tal I ered that the following valves which were originally judged to have accootable leak
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feedwater check valve 2821-F0108: and RHR ouro I I suction valves 2 Ell-F00aB, 2 Ell-FCoaC, and 2 Ell-F004D.
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i Cause Description and Corrective Action, This review showed that the acceptance criteria as specified in the Long Term Inservice Inspection Pump and Valve Test Plan (based en the suggest-ed values in Table IIN-3420-1 of ASME Section XI,..part IWV) are too string-ent to be realistically used.
This prcepted the licens~ee and Southern i
Company Services, Inc. to develop a new set of acceptance criteria (as per-l mitted by ASME Section XI, part IWV, paragraph IWV-3420, (f)).
This new I
set of acceptance criteria was then reviewed by the Plant Review Board and approved for replacing the old ones in the Pump and Valve Test Plan.
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NARRATIVE
SUMMARY t.
On May 23, 1979, while sh0tdown for anchor bolt inspection and repair, it was discovered that the folicwing valves which were originally judged to have acceptable leak rate values per Tech. Spec. 3.6.1.2 and Appendix J to 10CFR50 (based on overall leakage and concerned with limiting release to public) when tested per Ht:P-2-3952, did not meet the individual valve leak rate criteria per ASME Code,Section XI, part IWV:
feedwater check valve 2821-F010B; and RHR pump suction valves 2 Ell-f0048, 2 Ell-F004C, and 2 Ell-F004D.
It was originally interpreted that the ASME acceptance criteria did not 90 into effect until cc=ercial operation; however, the interpretation that it took effect with issuance of the operating li:ense (6-13-78) meant that any valves tested after 6-13-78 had to meet the ASME acceptance crit-i eria.
The above listed valves were all tested after E-13-78, and the leak-age value for each exceeded the ASME acceptance crite-ia as specified in j
i the HiiP-2 Long Term Inservice Inspection, thus the ASEE acceptance criter-ia was not met.
Follcwing the discovery that the valve leak rates had Exceeded the ASME leak rate acceptance criteria, a' review of the acceptance criteria was made by the licensee and Southern Coreany Services, Int This review showed that the acceptance criteria as specified in the HNP-2 Long Term Inservice Inspection Purp and Valve Test Plant (based on the sug:r-sted leak rate values in Table IWV-3220-1 of ASME -Section XI, Part IW'.1 are too stringent to be realistically used.
This prompted the licensee a:d SCSI to cevelop a new set of acceptance criteria (as permitted by ASME Eeccion XI, part IUV, paragraph IWV-3020, (f)).
Using the concept that the purpose of the ASME testing is to Jetect valve degradation, the license and SCSI were able to prepare rew acceptance criteria that would satisfy both the ASME and the Tech. Spec. and Appendix J testing consideratiers.
This new set of acceptance criteria was then reviewed by the Plant Re/iew Board and was approved for the replacement of the old acceptance c-iteria in the Pump and Valve Test Plan.
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| 05000366/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000366/LER-1979-001-03, /03L-0 on 781229:in Cold Shutdown While Performing HNP-2-3154,reactor Water Level Instrument Switch 1 Was Found Inoperative Due to Broken Foot, & Switch 3 Actuated at 122.2 in H2O Input | /03L-0 on 781229:in Cold Shutdown While Performing HNP-2-3154,reactor Water Level Instrument Switch 1 Was Found Inoperative Due to Broken Foot, & Switch 3 Actuated at 122.2 in H2O Input | | | 05000321/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000321/LER-1979-001-03, /03L-0 on 790109:during Steady State Power at 2400 Mwt,Plant Personnel Inadvertently Opened Both Doors of Reactor Bldg 130-ft Airlock R106.For Reasons Unknown,Switch Which Allows Defeat of Interlock Was Operated | /03L-0 on 790109:during Steady State Power at 2400 Mwt,Plant Personnel Inadvertently Opened Both Doors of Reactor Bldg 130-ft Airlock R106.For Reasons Unknown,Switch Which Allows Defeat of Interlock Was Operated | | | 05000321/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000321/LER-1979-002-03, /03L-0 on 790111:during Normal Operation,Hpci Steam Supply valves,E41-F002 & E41-F003,automatically Isolated Due to Equipment Room High Differential Temp & Cold Outside Air Flowing Across Inlet Air Temp Elements | /03L-0 on 790111:during Normal Operation,Hpci Steam Supply valves,E41-F002 & E41-F003,automatically Isolated Due to Equipment Room High Differential Temp & Cold Outside Air Flowing Across Inlet Air Temp Elements | | | 05000366/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000366/LER-1979-002-03, /03L-0 on 791231:in Cold Shutdown While Performing HNP-2-3456,overvoltage Trip Setpoint for Reactor Protection Sys Motor Generator Set B Was Found at 133.5 Volts Alternating Current.Caused by Setpoint Drift | /03L-0 on 791231:in Cold Shutdown While Performing HNP-2-3456,overvoltage Trip Setpoint for Reactor Protection Sys Motor Generator Set B Was Found at 133.5 Volts Alternating Current.Caused by Setpoint Drift | | | 05000321/LER-1979-003-03, /03L-0 on 790114:during Normal operation,hi-flow Alarm Occurred on Stack Effluent Radiation Monitor.Sample Pump Was Found Not Running.Restart Failed,As Did Spare Pump. Caused by Failure of Operating Pump Carbon Valves | /03L-0 on 790114:during Normal operation,hi-flow Alarm Occurred on Stack Effluent Radiation Monitor.Sample Pump Was Found Not Running.Restart Failed,As Did Spare Pump. Caused by Failure of Operating Pump Carbon Valves | | | 05000321/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000366/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000366/LER-1979-003-03, /03L-0 on 790102:in Cold Shutdown While Performing HNP-2-3173 on Reactor Pressure Switch 2B21-N021C,setpoint Found Above 600 Psig for Switch No 2.Caused by Switch Setpoint Drift | /03L-0 on 790102:in Cold Shutdown While Performing HNP-2-3173 on Reactor Pressure Switch 2B21-N021C,setpoint Found Above 600 Psig for Switch No 2.Caused by Switch Setpoint Drift | | | 05000321/LER-1979-004-03, /03L-0 on 790119:during Performance of Procedure HNP-1-3302,armature Winding of HPCI Injecting Valve Motor (E41-F006) Burned When Valve Was Opening.Minor Internal Disorder Probably Led to Overheat | /03L-0 on 790119:during Performance of Procedure HNP-1-3302,armature Winding of HPCI Injecting Valve Motor (E41-F006) Burned When Valve Was Opening.Minor Internal Disorder Probably Led to Overheat | | | 05000366/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000366/LER-1979-004-03, /03L-0 on 790104:review of HNP-2-3610-0 (RHR Pump Operability) Data Sheet Revealed Pump Delta Requirements Not Met.Caused by Personnel Error Resulting from New Procedures | /03L-0 on 790104:review of HNP-2-3610-0 (RHR Pump Operability) Data Sheet Revealed Pump Delta Requirements Not Met.Caused by Personnel Error Resulting from New Procedures | | | 05000321/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000366/LER-1979-005-03, /03L-0 on 790103:under Frequency Trip Setpoint Found at 54.1HZ for Motor Generator Set A.Caused by pre-op Test on Sys.Surveillance Test HNP-2-3456 Contains Setpoint More Conservative than Tech Specs | /03L-0 on 790103:under Frequency Trip Setpoint Found at 54.1HZ for Motor Generator Set A.Caused by pre-op Test on Sys.Surveillance Test HNP-2-3456 Contains Setpoint More Conservative than Tech Specs | | | 05000366/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000321/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000321/LER-1979-005-03, /03L-0 on 790118:while Performing HNP-1-350-M,TDR G31-R616D Failed to Actuate at Its Setting of 15-s.Two-h Time Limit Exceeded W/Sys Down for Repair.Caused by Loose Screw on Diaphragm,Resulting in Component Failure | /03L-0 on 790118:while Performing HNP-1-350-M,TDR G31-R616D Failed to Actuate at Its Setting of 15-s.Two-h Time Limit Exceeded W/Sys Down for Repair.Caused by Loose Screw on Diaphragm,Resulting in Component Failure | | | 05000366/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000366/LER-1979-006-03, /03L-0 on 790102:reactor Pressure Instrument Ft&C, Relay 2B21-K34A Failed to Operate W/Actuation of 2B21-N021A. Caused by Open Coil | /03L-0 on 790102:reactor Pressure Instrument Ft&C, Relay 2B21-K34A Failed to Operate W/Actuation of 2B21-N021A. Caused by Open Coil | | | 05000321/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000321/LER-1979-006-03, /03L-0 on 790122:during Normal Startup,Reactor Operated Above 1% for Over 24-h W/O Critical Mass Peaking Factor Being Calculated.Caused by Computer Limitations for Low Power Operation | /03L-0 on 790122:during Normal Startup,Reactor Operated Above 1% for Over 24-h W/O Critical Mass Peaking Factor Being Calculated.Caused by Computer Limitations for Low Power Operation | | | 05000321/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000321/LER-1979-007-03, /03L-0 on 790120:reactor Core Isolation Cooling Min Flow Valve (E51-F019) Failed to Close Automatically. Caused by Failure of Open Limit Switch,Resulting in Damage to Valve Operator & Torque Switch | /03L-0 on 790120:reactor Core Isolation Cooling Min Flow Valve (E51-F019) Failed to Close Automatically. Caused by Failure of Open Limit Switch,Resulting in Damage to Valve Operator & Torque Switch | | | 05000321/LER-1979-008-03, /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure | /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure | | | 05000366/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000366/LER-1979-008-03, /03L-0 on 790110:reactor Core Isolation Cooling Steam Line Differential Pressure Low Switch Found to Actuate at 119 in H2O & High Switch at +122 in H2O.Caused by Switch Setpoint Drift | /03L-0 on 790110:reactor Core Isolation Cooling Steam Line Differential Pressure Low Switch Found to Actuate at 119 in H2O & High Switch at +122 in H2O.Caused by Switch Setpoint Drift | | | 05000321/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000366/LER-1979-009-03, /03L-0 on 790111:low Switch & High Switch of 2E51-NO18 Operated Contrary to Tech Specs.Caused by Switch Setpoint Drift.Corrected by Performance of HNP-2-5202 Procedure | /03L-0 on 790111:low Switch & High Switch of 2E51-NO18 Operated Contrary to Tech Specs.Caused by Switch Setpoint Drift.Corrected by Performance of HNP-2-5202 Procedure | | | 05000366/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000321/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000321/LER-1979-009-03, /03L-0 on 790123:during Normal Operation,While Performing Maint on Reactor Water Cleanup Pumps,Personnel Unable to Sample Primary Coolant Every 4-h.Caused by Stopped Up Redundant Sample Line | /03L-0 on 790123:during Normal Operation,While Performing Maint on Reactor Water Cleanup Pumps,Personnel Unable to Sample Primary Coolant Every 4-h.Caused by Stopped Up Redundant Sample Line | | | 05000321/LER-1979-010-03, /03L-0 on 790124:during Normal pre-conditional Ramp,Determined That a Reactor Coolant Chemistry Sample Could Not Be Obtained.Caused by Both Reactor Water Cleanup Pumps Being Inoperable & Primary Sample Line Clogged | /03L-0 on 790124:during Normal pre-conditional Ramp,Determined That a Reactor Coolant Chemistry Sample Could Not Be Obtained.Caused by Both Reactor Water Cleanup Pumps Being Inoperable & Primary Sample Line Clogged | | | 05000321/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000366/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000366/LER-1979-010-03, /03L-0 on 790117:in Cold Shutdown,While Performing HNP-2-3820,switches 2B21-N301 F,H & L Did Not Actuate.Caused by Switch Diaphragm Failure | /03L-0 on 790117:in Cold Shutdown,While Performing HNP-2-3820,switches 2B21-N301 F,H & L Did Not Actuate.Caused by Switch Diaphragm Failure | | | 05000321/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000366/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000366/LER-1979-011-03, /03L-0 on 790117:during Normal Startup Test & Reactor in Cold Shutdown,Review of HNP-2-3160 (RHR Pump Operability) Revealed Required Flow Not Being Met.Caused by Procedural Error by Personnel | /03L-0 on 790117:during Normal Startup Test & Reactor in Cold Shutdown,Review of HNP-2-3160 (RHR Pump Operability) Revealed Required Flow Not Being Met.Caused by Procedural Error by Personnel | | | 05000321/LER-1979-011-03, /03L-0 on 790124:while in Cold Shutdown,Both Doors of Reactor Bldg Were Opened,Violating Secondary Containment. Bracket Into Which Dead Bolt Projects Was Bent,Preventing Interlock from Functioning.Bracket Was Repaired | /03L-0 on 790124:while in Cold Shutdown,Both Doors of Reactor Bldg Were Opened,Violating Secondary Containment. Bracket Into Which Dead Bolt Projects Was Bent,Preventing Interlock from Functioning.Bracket Was Repaired | | | 05000366/LER-1979-012, Has Been Voided | Has Been Voided | | | 05000321/LER-1979-012-03, /03L-0 on 790124:during Shutdown,High Pressure of 200 to 300 Psig Existed in RHR Heat Exchangers.Caused by Slow Leak Past E11-F015A Valve | /03L-0 on 790124:during Shutdown,High Pressure of 200 to 300 Psig Existed in RHR Heat Exchangers.Caused by Slow Leak Past E11-F015A Valve | | | 05000321/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000366/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000321/LER-1979-013-01, /01X-1 on 790131:scram Received on Intermediate Range Monitor Hi-Hi Trip at Notch 26 of Rod 42-15.Caused by Notches Being Withdrawn Past Point Required to Achieve Criticality.Procedures Revised | /01X-1 on 790131:scram Received on Intermediate Range Monitor Hi-Hi Trip at Notch 26 of Rod 42-15.Caused by Notches Being Withdrawn Past Point Required to Achieve Criticality.Procedures Revised | | | 05000366/LER-1979-013-03, /03L-0 on 790125:while in Refuel Mode,Control Rod & Control Rod Drive Removal Was Begun Before Performing one- Rod Out Refueling Interlock Operability Test.Caused by Omission of This Step in Procedure.Procedure to Be Revised | /03L-0 on 790125:while in Refuel Mode,Control Rod & Control Rod Drive Removal Was Begun Before Performing one- Rod Out Refueling Interlock Operability Test.Caused by Omission of This Step in Procedure.Procedure to Be Revised | | | 05000321/LER-1979-013, Foward LER 79-013/01X-1 | Foward LER 79-013/01X-1 | | | 05000321/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | |
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