05000364/LER-1999-001-05, :on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change1999-07-0202 July 1999
- on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change
ML20196J3791999-06-30030 June 1999
Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable
ML20209G0661999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000348/LER-1999-002-02, :on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With1999-06-25025 June 1999
- on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With
ML20206L4551999-05-10010 May 1999
Safety Evaluation Supporting Amends 142 & 134 to Licenses NPF-2 & NPF-8,respectively
ML20206G7471999-05-0404 May 1999
Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07
ML20206C9461999-04-30030 April 1999
1:Final Cycle 16 Freespan ODSCC Operational Assessment
ML20204D4391999-03-31031 March 1999
Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept
ML20204D7271999-03-15015 March 1999
ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1
ML20207M6421999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20203J0631999-02-19019 February 1999
Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-2 & NPF-8,respectively
ML20203A2651999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With
05000348/LER-1998-008-01, :on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With1999-01-18018 January 1999
- on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With
ML20199D8611999-01-12012 January 1999
SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2
ML20198S4091999-01-0606 January 1999
Revised SE Supporting Amends 140 & 132 to Licenses NPF-2 & NPF-8,respectively.Page Contains Vertical Lines to Indicate Areas of Change
ML20199E6591998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20206C8081998-12-31031 December 1998
Alabama Power 1998 Annual Rept
05000348/LER-1998-007-02, :on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required1998-12-22022 December 1998
- on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required
05000348/LER-1998-006-03, :on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met1998-12-18018 December 1998
- on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met
ML20198K4091998-12-18018 December 1998
COLR for Jm Farley,Unit 1 Cycle 16
05000364/LER-1998-007-01, :on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With1998-12-11011 December 1998
- on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With
ML20198B2561998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20195E2281998-11-16016 November 1998
Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1
05000348/LER-1998-005-03, :on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With1998-11-12012 November 1998
- on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With
ML20155H4801998-11-0303 November 1998
Safety Evaluation Supporting Amends 139 & 131 to Licenses NPF-2 & NPF-8,respectively
ML20195C9681998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20155E0271998-10-29029 October 1998
SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04
ML20154L2871998-10-15015 October 1998
Safety Evaluation Supporting Amends 138 & 130 to Licenses NPF-2 & NPF-8,respectively
ML20154B6121998-10-0101 October 1998
Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1
ML20154H6001998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With
ML20154H0121998-09-30030 September 1998
Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion)
ML20151V8341998-09-30030 September 1998
Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change
05000348/LER-1998-004-03, :on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With1998-09-28028 September 1998
- on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With
05000348/LER-1998-003-04, :on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With1998-09-11011 September 1998
- on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With
05000348/LER-1997-003, :on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With1998-09-0808 September 1998
- on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With
05000348/LER-1998-005, :on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures1998-09-0303 September 1998
- on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures
05000348/LER-1998-002-05, :on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced1998-09-0303 September 1998
- on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced