Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20199G1991997-11-19019 November 1997 Corrected Page 4-12 to WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept ML20148M7841997-06-30030 June 1997 Non-proprietary Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for AL Power Farley Nuclear Plant Units 1 & 2, Rev 1 ML20212D2621997-04-30030 April 1997 Rev 1 to WCAP-14689, Farley,Units 1 & 2,Heatup & Cooldown Limit Curves for Normal Operation & PTLR Support Documentation ML20135C9731997-01-31031 January 1997 Non-proprietary Version of WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept ML20133G6011997-01-31031 January 1997 Specific Application of Laser Welded Sleeves for Farley Units 1 & 2 Sg ML20133G5901997-01-31031 January 1997 Rev 4 to W Series 44 & 51 SG Generic Sleeving Rept,Laser Welded Sleeves ML20149L9111996-11-0606 November 1996 Nonproprietary Class 3 SG Sleeving Integration Rept for Jm Farley Units 1 & 2 ML20128M5411996-10-0808 October 1996 L* Tube Plugging Criteria for Tubes W/Degradation in Tubesheet Roll Expansion Region of Farley Unit 2 Sg ML20135B8261996-09-30030 September 1996 RCS Flow Verification Using Elbow Taps at Westinghouse 3- Loop Pwrs ML20212D2551996-06-30030 June 1996 Jm Farley,Units 1 & 2,Radiation Analysis & Neutron Dosimetry Evaluation ML20087E8311995-08-31031 August 1995 Elimination of Pressure Sensor Response Time Testing Requirements,Wog Program MUHP-3040 Rev 1 ML20080S5261995-03-31031 March 1995 Evaluation of PTS for Farley Units 1 & 2 ML20080S5121995-02-28028 February 1995 Analysis of Capsule W from Apco Farley Unit 1 Reactor Vessel Radiation Surveillance Program ML20069K2921994-03-31031 March 1994 Nonproprietary Steam Generator Lower Level Tap Relocation Assessment for Jm Farley Nuclear Plant Units 1 & 2 ML20072F3661993-12-31031 December 1993 Elimination of Pressure Sensor Response Time Testing Requirements ML20114B5131992-08-31031 August 1992 Nonproprietary PWR SG Tube Repair Limits:Technical Support Document for Outside Diameter Stress Corrosion Cracking at Tube Support Plates Final Rept ML20114B5011992-08-31031 August 1992 Nonproprietary Response to NRC Questions on Farley SG Tube Alternate Plugging Criteria Presentation Matls ML20101G2901992-03-31031 March 1992 Nonproprietary Preliminary Data on Voltage/Burst/Leakage of 3/4 Inch Diameter Tubing for ODSCC at Tsps ML20094J9681992-02-29029 February 1992 Nonproprietary Jm Farley Units 1 & 2 SG Tube Plugging Criteria for Outer Diameter Stress Corrosion Cracking at Tube Support Plates ML20092M9471992-02-29029 February 1992 Steam Generator Tube Alternate Plugging Criteria Presentation Matls ML20090B9511992-02-28028 February 1992 Nonproprietary Rev 2 to RTD Bypass Elimination for Licensing Rept for Jm Farley Nuclear Plant,Units 1 & 2, Table 2.1-1 (Replacement Page 15) ML20092J1281991-12-31031 December 1991 Nonproprietary WCAP-13139, Steam Generator Tube Support Plate Alternate Plugging Criteria Summary ML20086A0421991-10-31031 October 1991 Nonproprietary Addl Info Supporting SG TSP Criteria for Jm Farley,Units 1 & 2 ML20086A0611991-10-31031 October 1991 Rev 1 to WCAP-12872, Jm Farley Units 1 & 2 SG Tube Plugging Criteria for ODSCC at Tsp ML20082T4381991-09-30030 September 1991 Nonproprietary Addl Info in Support of Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Jm Farley Plant Units 1 & 2 ML20082S7461991-08-31031 August 1991 Nonproprietary Jm Farley Nuclear Plant Units 1 & 2 Response to NRC Request for Addl Info on Steam Generator Flow Area Reduction Due to Combined LOCA & SSE Loads ML20092L1911991-07-31031 July 1991 Rev 2 to Handbook on Flaw Evaluation for Joseph Farley Units 1 & 2 Steam Generators & Pressurizers ML20079D6071991-05-31031 May 1991 Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loop Elimination) ML20079D6031991-05-31031 May 1991 Westinghouse Revised Thermal Design Procedure Instrument Uncertainity Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loops) ML20073P1261991-05-31031 May 1991 Allowable Outage Time Study for RHR Valves for Farley Nuclear Plant,Units 1 & 2 ML20073J9891991-04-30030 April 1991 Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Farley Units 1 & 2 ML20066J5661991-01-31031 January 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Jm Farley Units 1 & 2 Nuclear Power Plants ML20066L3171991-01-31031 January 1991 Nonproprietary WCAP-12856, Structural Evaluation of Farley Units 1 & 2 Pressurizer Surge Lines,Considering Effects of Thermal Stratification ML20066L0501991-01-31031 January 1991 Nonproprietary Rev 2 to WCAP 12614, RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 ML20066E5091990-12-31031 December 1990 Nonproprietary Steam Generator Tube Plugging Limits Presentation Matls ML20197H6651990-11-30030 November 1990 Nonproprietary WCAP-12764, Steam Generator Tube Collapse Considerations Presentation Matls ML20058E3851990-10-26026 October 1990 Rev 1 to RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 ML20058E3551990-08-31031 August 1990 Rev 0 to Alabama Power Jm Farley Unit 1 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept ML20059D4851990-08-16016 August 1990 Steam Generator Sleeving Rept Laser Welded Sleeves Jm Farley Units 1& 2 ML20058E3661990-07-31031 July 1990 Median Signal Selector for Westinghouse 7300 Series Process Instrumentation - Application to Westinghouse Three Loop Plants Employing RTD Bypass Elimination,Alabama Light Co, Jm Farley Unit 1 ML20059D4371990-07-31031 July 1990 Alabama Power Jm Farley Unit 2 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept ML20062F9781990-07-31031 July 1990 Rev 1 to WCAP-12213, Handbook on Flaw Evaluation for J Farley Units 1 & 2 Steam Generators & Pressurizers ML20062F9761989-09-30030 September 1989 Nonproprietary WCAP-12447, Background & Technical Basis: Handbook on Flaw Evaluation for Farley Units 1 & 2 Main Coolant Sys & Components ML20247N0321989-07-31031 July 1989 Nonproprietary Jm Farley Unit 2 Engineering Evaluation of Weld Joint Crack in 6-Inch Safety Injection & RHR Piping ML20058N8181988-12-31031 December 1988 Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Jm Farley Nuclear Plant Units 1 & 2 ML20153D7051988-07-31031 July 1988 Joseph Farley Unit 1 & 2 Evaluation for Tube Vibration Induced Fatigue ML20153D6621988-04-30030 April 1988 Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds ML20210D3041987-04-30030 April 1987 Rev 2 to Tubesheet Region Plugging Criterion for Alabama Power Co Farley Nuclear Station Unit 2 Steam Generators ML20210D2831987-04-30030 April 1987 Rev 1 to Jm Farley Units 1 & 2 Steam Generator Sleeving Rept (Mechanical Sleeves) ML20210T5711986-06-30030 June 1986 Rev 2 to Heatup & Cooldown Limit Curves for Alabama Power Co,Joseph M Farley Unit 1 Reactor Vessel 1997-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20211B8931999-08-17017 August 1999 Safety Evaluation Supporting Amend 143 to License NPF-2 ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 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
ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable 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
L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. 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 L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 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 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
ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
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