LER-1979-021, /01T-3 on 790412:statistical Sampling of Seismic Category I Anchor Bolts Would Not Provide Probability Greater than 95% Reliability.Caused Under Investigation. Testing Extended to 100% Verification of Anchors on Pipe |
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U.S. NUCLEAH HEGULAToHY CoMMihSION NRC FCRM OGG s
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REPCHT DATE 80 EVENT DESCRIPTION AND PROSA8LE CONSECUENCES h o
2 lIn response to IE Bulletin 79-02, Alabama Power Company initiated a program to I
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ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO. 50-348 ATTACHMENT TO LER 79-021/0lT-3 Facility:
Joseph M. Farley Unit 1 Report Date:
6/19/79 Event Date:
4/12/79 Identification of Event Potential for anchor bolt failures and the resultant possibility of hanger failure in certain systems.
Conditions Prior to Event
The unit was in mode 6 (refueling).
Description of Event
In response to IE Bulletin 79-02, Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category I, Safety Related, 2 inch and greater piping systems.
Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. The potential for anchor bolt failures and the resultant possibility of hanger failure were reported to the NRC on 4/12/79 under the potential applicability of Technical Specification 6.9.1.8(i).
Subject bolts were manufactured by Phillips Drill Co., Hilti Fastening Systems Incorporated and Wej-It Corporation.
Designation of Apparent Cause Under investigation.
Analysis of Event
Alabama Power Company initiated a program to randomly select and test a sample of anchor bolts installed in Seismic Category I, Safety Related, 2 inch and greater piping systems.
Initial results of that program revealed that statistical sampling would not be sufficient to provide a high probability of greater than 95% anchor bolt reliability. Also, it has been found that design, documentation and installation deficiencies exist on pipe hangers. The health and safety of the public is not affected.
2238 201
79-021/01T-3
Corrective Action
The anchor bolt testing program has been expanded to include 100%
verification of acceptable anchors on pipe hangers for those systems or portions of systems required to meet design basis accidents and those required to bring the plant to cold shutdown.
This piping includes:
Seismic Category I; Safety-Related 2-1/2 inch and above.
a.
b.
Seismic Category I; Safety-Related Class I under 2-1/2 inch.
Seismic Category I; Safety-Related of other classes for which c.
the designer performed detailed analysis, d.
All piping through containment penetrations.
The systems involved in the above verification include the following:
1.
Component Cooling Water System 2.
Service Water System 3.
Sampling System 4.
Chemical Volume and Control System 5.
Residual Heat Removal System 6.
Main Steam System 7.
Containment Cooling System 8.
Reactor Coolant System 9.
Emergency Core Cooling System 10.
Main Feedwater System 11.
Emergency Diesel Generator with Fuel Oil System 12.
Gaseous Waste System 13.
Post Accident Containment Hydrogen Control System 14.
Auxiliary Feedwater System 15.
Containment Spray System 16.
Condensate Storage Tank 202
79-021/01T-3 17.
Containment Isolation System 18.
Main Steam Safety and Relief Valve Systems The overall scope of the above verification program includes approximately.12,000 anchor bolts.
Engineering design organizations are participating in determining test acceptance criteria which will ensure proper anchor bolt safety margins. Designers will verify the adequacy of pipe hangers within the verification program. This will include verification of hanger design and anchor bolt loadings. The necessary corrective action will be accomplished on each system to ensure operability.
The results of the verification will be included in the evaluation covering all portions of all Seismic Category I systems required by IE Bulletin 79-02.
A supplemental LER will be submitted when corrective actions required have been identified. Farley Nuclear Plant will not return to power range reactor operation until such time as Alabama Power Company and NRC Region II mutually agree that potential safety questions have been satisfactorily resolved.
Failure Data None 2238 203
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| 05000348/LER-1979-001-03, /03L-0 on 790109:electronic Switching Sys B1G Sequencer Failed to Meet Time Requirements for Picking Up Step 2.Caused by Agastat Timer Setpoint Drift | /03L-0 on 790109:electronic Switching Sys B1G Sequencer Failed to Meet Time Requirements for Picking Up Step 2.Caused by Agastat Timer Setpoint Drift | | | 05000348/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000348/LER-1979-002-03, /03L-0 on 790116:120V Vital AC Bus 1B Was Deenergized When Inverter 1B Tripped Due to Components Failure.Capacitor,Air Core Choke,Resistor & Fuse Were Replaced & Inverter Returned to Svc | /03L-0 on 790116:120V Vital AC Bus 1B Was Deenergized When Inverter 1B Tripped Due to Components Failure.Capacitor,Air Core Choke,Resistor & Fuse Were Replaced & Inverter Returned to Svc | | | 05000348/LER-1979-003-03, /03L-0 on 790116:following Reactor Trip,Turbine Driven Auxiliary Feedwater Pump Failed to Start.Caused by Trip/Throttle Valve Which Tripped Shut | /03L-0 on 790116:following Reactor Trip,Turbine Driven Auxiliary Feedwater Pump Failed to Start.Caused by Trip/Throttle Valve Which Tripped Shut | | | 05000348/LER-1979-004-03, /03L-0 on 790123:containment Atmosphere Particulate Radioactivity Monitoring Sys Inoperable;Filter Paper Was Not Advancing.Caused by Replacement Paper Being Thicker That That Originally Supplied | /03L-0 on 790123:containment Atmosphere Particulate Radioactivity Monitoring Sys Inoperable;Filter Paper Was Not Advancing.Caused by Replacement Paper Being Thicker That That Originally Supplied | | | 05000348/LER-1979-005, /03L-0 on 790123:during Maint on Boron Injection Tank Inlet Valve Q1E21VO16B,boron Concentration Fell Below Tech Spec Requirements.Caused by Leakage Through Opened Valve During Troubleshooting Per LER 79-005/03L-0 | /03L-0 on 790123:during Maint on Boron Injection Tank Inlet Valve Q1E21VO16B,boron Concentration Fell Below Tech Spec Requirements.Caused by Leakage Through Opened Valve During Troubleshooting Per LER 79-005/03L-0 | | | 05000348/LER-1979-005-03, /03L-0 on 790123:during Surveillance Test on Boron Injection Tank Inlet Valve Q1E32V016B,valve Failed to Operate Electrically.Cause Undetermined,Since Subsequent Troubleshooting Failed to Duplicate Problem | /03L-0 on 790123:during Surveillance Test on Boron Injection Tank Inlet Valve Q1E32V016B,valve Failed to Operate Electrically.Cause Undetermined,Since Subsequent Troubleshooting Failed to Duplicate Problem | | | 05000348/LER-1979-007-03, /03L-0 on 790212:during Review of Surveillance Test Data,Noted That RCS Leakage Test (FNP-1-STP-9.0) Had Not Been Done within Time Specified.Caused by Personnel Failure.Supervisors Instructed Re Matter | /03L-0 on 790212:during Review of Surveillance Test Data,Noted That RCS Leakage Test (FNP-1-STP-9.0) Had Not Been Done within Time Specified.Caused by Personnel Failure.Supervisors Instructed Re Matter | | | 05000348/LER-1979-007, Forwards LER 79-007/03L-0,LER 79-008/03L-0,LER 79-009/03L-0, LER 79-010/03L-0, & 79-011/03L-0 | Forwards LER 79-007/03L-0,LER 79-008/03L-0,LER 79-009/03L-0, LER 79-010/03L-0, & 79-011/03L-0 | | | 05000348/LER-1979-008-03, /03L-0 on 790216:during Review of Surveillance Test FNP-1-STP-15.0,containment Main Personnel & Emergency Air Leak Outer Doors Failed to Meet Acceptance Criteria. Leakage Probably Caused by Dirty Door Seals &/Or Seal Set | /03L-0 on 790216:during Review of Surveillance Test FNP-1-STP-15.0,containment Main Personnel & Emergency Air Leak Outer Doors Failed to Meet Acceptance Criteria. Leakage Probably Caused by Dirty Door Seals &/Or Seal Set | | | 05000348/LER-1979-009-03, /03L-0 on 790216:during Plant Startup W/Reactor & Steam Generator Controls Manual & Steam Dumps in Automatic, Steam Dumps Occurred.Temp Average Reduced to 538 F.Personnel Reinstructed | /03L-0 on 790216:during Plant Startup W/Reactor & Steam Generator Controls Manual & Steam Dumps in Automatic, Steam Dumps Occurred.Temp Average Reduced to 538 F.Personnel Reinstructed | | | 05000348/LER-1979-010-03, /03L-0 on 790218:while Doing FNP-1-STP-215.1B, Steam Flow/Feed Flow Bistable (FB478A)failed to Meet Table 2-1 Trip Setpoint Valve.Caused by Bistable Setpoint Drift Below That Specified in Surveillance Test.Bistable Adjusted | /03L-0 on 790218:while Doing FNP-1-STP-215.1B, Steam Flow/Feed Flow Bistable (FB478A)failed to Meet Table 2-1 Trip Setpoint Valve.Caused by Bistable Setpoint Drift Below That Specified in Surveillance Test.Bistable Adjusted | | | 05000348/LER-1979-011-03, /03L-0 on 790221:while Doing FNP-1-STP-28.7,LOSP B1F Sequencer Failed to Meet Time Requirement for Picking Up Step 6.Caused by Agastat Timer Setpoint Drift.Agastat Timer Adjusted & Satisfactorily Retested | /03L-0 on 790221:while Doing FNP-1-STP-28.7,LOSP B1F Sequencer Failed to Meet Time Requirement for Picking Up Step 6.Caused by Agastat Timer Setpoint Drift.Agastat Timer Adjusted & Satisfactorily Retested | | | 05000348/LER-1979-012-03, /03L-0 on 790214:review of Solid State Protective Sys Train A/B Operability Test Indicated That Portion of Program Did Not Verify Spray Test Actuation Logic.Caused by Sys Train Design Change.Procedure Modified | /03L-0 on 790214:review of Solid State Protective Sys Train A/B Operability Test Indicated That Portion of Program Did Not Verify Spray Test Actuation Logic.Caused by Sys Train Design Change.Procedure Modified | | | 05000348/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000348/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000348/LER-1979-013-03, /03L-0 on 790227:B1F Sequencer Found in Test Mode, Rendering 1-2A Diesel Generator Inoperable.Caused by Faulty Switch Mechanism.Sequencer Repaired | /03L-0 on 790227:B1F Sequencer Found in Test Mode, Rendering 1-2A Diesel Generator Inoperable.Caused by Faulty Switch Mechanism.Sequencer Repaired | | | 05000348/LER-1979-015-01, /01T-0 on 790327:during Inservice Insp,Linear Svc Indications Found on ECCS Line to Loops 1 & 2 Cold Legs & Loop 3 Hot Leg.Caused During Handling.Two Corrective Actions Proposed:Cut Out & Replace or Grind Out | /01T-0 on 790327:during Inservice Insp,Linear Svc Indications Found on ECCS Line to Loops 1 & 2 Cold Legs & Loop 3 Hot Leg.Caused During Handling.Two Corrective Actions Proposed:Cut Out & Replace or Grind Out | | | 05000348/LER-1979-016-03, /03L-0 on 790325:loss of Sys Pressure B1F Sequencer Failed to Meet Time Requirements in Test.Agastat Timer Setpoint Drifted Below Setpoint Required for Test. Timer Adjusted;Test Redone | /03L-0 on 790325:loss of Sys Pressure B1F Sequencer Failed to Meet Time Requirements in Test.Agastat Timer Setpoint Drifted Below Setpoint Required for Test. Timer Adjusted;Test Redone | | | 05000348/LER-1979-017-01, /01T-2 on 790330:util Notified by Westinghouse of Single Dropped Rod W/Potential for Calculated DNB Ratios Lower than Reported to NRC for Floating Nuclear Plants. Caused by Incorrect Measurement During Rod Drop Events | /01T-2 on 790330:util Notified by Westinghouse of Single Dropped Rod W/Potential for Calculated DNB Ratios Lower than Reported to NRC for Floating Nuclear Plants. Caused by Incorrect Measurement During Rod Drop Events | | | 05000348/LER-1979-017, Forwards LER 79-017/01T-2 | Forwards LER 79-017/01T-2 | | | 05000348/LER-1979-019, Forwards LER 79-019/03L-1 | Forwards LER 79-019/03L-1 | | | 05000348/LER-1979-019-03, /03L-1 on 790420:fluoride & Chloride Concentrations in RCS in Violation of Tech Spec Limits.Cause Not Determined.Rcs Integrity Not Impaired & Acceptable for Continued Operation | /03L-1 on 790420:fluoride & Chloride Concentrations in RCS in Violation of Tech Spec Limits.Cause Not Determined.Rcs Integrity Not Impaired & Acceptable for Continued Operation | | | 05000348/LER-1979-021-01, /01T-3 on 790412:statistical Sampling of Seismic Category I Anchor Bolts Would Not Provide Probability Greater than 95% Reliability.Caused Under Investigation. Testing Extended to 100% Verification of Anchors on Pipe | /01T-3 on 790412:statistical Sampling of Seismic Category I Anchor Bolts Would Not Provide Probability Greater than 95% Reliability.Caused Under Investigation. Testing Extended to 100% Verification of Anchors on Pipe | | | 05000348/LER-1979-021, Forwards LER 79-021/01T-3 | Forwards LER 79-021/01T-3 | | | 05000348/LER-1979-022-03, /03L-0 on 790620:surveillance Test Procedure FNP-1-STP-29.2 Not Performed on 790620.Caused by Inadequate Surveillance Test Schedule Review by Shift Foreman on 790620.Importance of Accurate Daily Review Stressed | /03L-0 on 790620:surveillance Test Procedure FNP-1-STP-29.2 Not Performed on 790620.Caused by Inadequate Surveillance Test Schedule Review by Shift Foreman on 790620.Importance of Accurate Daily Review Stressed | | | 05000348/LER-1979-023-01, /01T-0 on 790622:notified by Westinghouse That High Energy Line Break Inside Containment Could Cause Heatup of Steam Generator Level Transmitter Ref Legs. LER Will Be Issued Upon Completion of Investigation | /01T-0 on 790622:notified by Westinghouse That High Energy Line Break Inside Containment Could Cause Heatup of Steam Generator Level Transmitter Ref Legs. LER Will Be Issued Upon Completion of Investigation | | | 05000348/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000348/LER-1979-024-03, /03L-0 on 790622:during Review of Surveillance Tests FNP-1-STP-40.1 & 40.2,noted That Certain Components Were Not Included in Test Procedures.Caused by Procedural Deficiencies.Procedure Change Has Been Made | /03L-0 on 790622:during Review of Surveillance Tests FNP-1-STP-40.1 & 40.2,noted That Certain Components Were Not Included in Test Procedures.Caused by Procedural Deficiencies.Procedure Change Has Been Made | | | 05000348/LER-1979-025-03, /03L-0 on 790623:during Surveillance Test FNP-1-STP-256.11 Both Source Range Channels Inadvertently Were Deenergized. Caused by Procedure Deficiency. Power Restored & Procedure Changed | /03L-0 on 790623:during Surveillance Test FNP-1-STP-256.11 Both Source Range Channels Inadvertently Were Deenergized. Caused by Procedure Deficiency. Power Restored & Procedure Changed | | | 05000348/LER-1979-026-03, /03L-0 on 790716:total of 135 Hydraulic Snubbers Did Not Meet Surveillance Test Requirements.Caused by Loss of Oil Due to Seal Leakage & Failure to Meet Lockup & Bleed Acceptance Criteria.Snubbers Repaired & Tested | /03L-0 on 790716:total of 135 Hydraulic Snubbers Did Not Meet Surveillance Test Requirements.Caused by Loss of Oil Due to Seal Leakage & Failure to Meet Lockup & Bleed Acceptance Criteria.Snubbers Repaired & Tested | | | 05000348/LER-1979-027-03, /03L-0 on 790607:radiation Monitor Declared Inoperable.Caused by Pump Malfunction.Pump Repaired & Declared Operable 790615 | /03L-0 on 790607:radiation Monitor Declared Inoperable.Caused by Pump Malfunction.Pump Repaired & Declared Operable 790615 | | | 05000348/LER-1979-028-03, /03L-0 on 790627:radiation Monitor R-5 Declared Inoperable Due to Loss of Power.Feedbreaker Found Open. Cause Unknown.Breaker Closed & R-5 Declared Operable | /03L-0 on 790627:radiation Monitor R-5 Declared Inoperable Due to Loss of Power.Feedbreaker Found Open. Cause Unknown.Breaker Closed & R-5 Declared Operable | | | 05000348/LER-1979-029-03, /03L-0 on 790713:penetration Room Filtration Sys Trains a & B Inoperable.Caused by Train B Exhaust Fan Not Starting & Train a Suction Damper Not Opening.Overload Reset & Fuse Replaced | /03L-0 on 790713:penetration Room Filtration Sys Trains a & B Inoperable.Caused by Train B Exhaust Fan Not Starting & Train a Suction Damper Not Opening.Overload Reset & Fuse Replaced | | | 05000348/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000348/LER-1979-030, Forwards LER 79-030/03L-0 | Forwards LER 79-030/03L-0 | | | 05000348/LER-1979-030-03, /03L-0 on 790717:during Surveillance test,600 Volt Ctr 1C Supply Breaker EE07 Failed to Load Shed.Caused by Open Links in Local Control Panel.Links Closed & Breaker Verified | /03L-0 on 790717:during Surveillance test,600 Volt Ctr 1C Supply Breaker EE07 Failed to Load Shed.Caused by Open Links in Local Control Panel.Links Closed & Breaker Verified | | | 05000348/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000348/LER-1979-031-03, /03L-0 on 790717:two Control Power Fuses Blew in N31 Source Range Drawer & Were Causing Loss of Power in Both Source Range Channels.Caused by Personnel Error | /03L-0 on 790717:two Control Power Fuses Blew in N31 Source Range Drawer & Were Causing Loss of Power in Both Source Range Channels.Caused by Personnel Error | | | 05000348/LER-1979-032-03, /03L-0:on 790730,determined That Diesel Generators 1C & 2C Output Breakers Were Racked Out.Caused by Personnel Error.Breakers Racked in & Control Power Restored | /03L-0:on 790730,determined That Diesel Generators 1C & 2C Output Breakers Were Racked Out.Caused by Personnel Error.Breakers Racked in & Control Power Restored | | | 05000348/LER-1979-033-03, /03L-0:on 790803,radiation Monitor R25B Declared Inoperable.Caused by Drive Belt Failure.New Drive Belt Installed | /03L-0:on 790803,radiation Monitor R25B Declared Inoperable.Caused by Drive Belt Failure.New Drive Belt Installed | | | 05000348/LER-1979-034, Forwards LER 79-034/03L-0 | Forwards LER 79-034/03L-0 | | | 05000348/LER-1979-034-03, /03L-0:on 790824,determined That Functional Surveillance Test Had Not Been Performed on Certain Seismic Monitoring Instrumentation within Specified Time.Caused by Personnel Error.Proper Procedure re-emphasized | /03L-0:on 790824,determined That Functional Surveillance Test Had Not Been Performed on Certain Seismic Monitoring Instrumentation within Specified Time.Caused by Personnel Error.Proper Procedure re-emphasized | | | 05000348/LER-1979-035, Forwards LER 79-035/01T-0 | Forwards LER 79-035/01T-0 | | | 05000348/LER-1979-035-01, /01T-0:on 790824,Westinghouse Notified Util of Potential Heat Sink Shorting to 7300 Rack Card Guides within 7300 Process Instrumentation & Control Printed Card Circuits.Caused by Mfg Defect.Cards Replaced | /01T-0:on 790824,Westinghouse Notified Util of Potential Heat Sink Shorting to 7300 Rack Card Guides within 7300 Process Instrumentation & Control Printed Card Circuits.Caused by Mfg Defect.Cards Replaced | | | 05000348/LER-1979-036-03, /03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves | /03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves | | | 05000348/LER-1979-037-03, /03L-0:on 790906,auxiliary Bldg Battery Verification Was Two Days Late.Caused by Personnel Error. Performance of Surveillance Tests on Scheduled Dates Will Be Discussed W/Affected Personnel | /03L-0:on 790906,auxiliary Bldg Battery Verification Was Two Days Late.Caused by Personnel Error. Performance of Surveillance Tests on Scheduled Dates Will Be Discussed W/Affected Personnel | | | 05000348/LER-1979-038-03, /03L-0:on 790912,while Performing Surveillance Test FNP-1-STP-1.0,containment Gaseous Activity Purge & Exhaust Isolation Monitor Declared Inoperable.Caused by Monitor Bypass Valve Being in Open Position | /03L-0:on 790912,while Performing Surveillance Test FNP-1-STP-1.0,containment Gaseous Activity Purge & Exhaust Isolation Monitor Declared Inoperable.Caused by Monitor Bypass Valve Being in Open Position | | | 05000348/LER-1979-039-03, /03L-0:on 790924,fuel Storage Pool Area Radiation Monitor Declared Inoperable Due to Reading Discrepancy. Caused by Instrument Drift.Monitor Recalibr & Returned to Svc on 790930 | /03L-0:on 790924,fuel Storage Pool Area Radiation Monitor Declared Inoperable Due to Reading Discrepancy. Caused by Instrument Drift.Monitor Recalibr & Returned to Svc on 790930 | | | 05000348/LER-1979-040-01, /01T-0:on 791011,wrong Valves Installed in Piping Sys.Caused by Deficiency in Original Plant Design Equipment Specs.Valves Being Replaced | /01T-0:on 791011,wrong Valves Installed in Piping Sys.Caused by Deficiency in Original Plant Design Equipment Specs.Valves Being Replaced | |
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