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 Issue dateTitle
ML23319A06831 October 20231 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
IR 05000348/202309031 August 2023NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation
NL-21-0912, 0 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features28 October 20210 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
ML21260A16124 September 2021Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)3 May 2019Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)
IR 05000348/20190113 April 2019NRC Problem Identification and Resolution Inspection Report 05000348/2019011 and 05000364/2019011
IR 05000348/201800413 February 2019NRC Integrated Inspection Report 05000348/2018004 and 05000364/2018004
NL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...27 July 2018License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...
ML18065A0256 March 2018Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures
ML20311A5796 November 20172017 Q1-Q4 ROP Inspection Findings
05000364/LER-2017-00121 August 20172B Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability
LER 17-001-00 for Farley, Unit 2, Regarding 28 Emergency Diesel Generator Rendered Inoperable Due to a Jacket Water Leak without Makeup Capability
NL-17-0480, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information22 June 2017License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information
NL-17-0774, Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating15 May 2017Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating
ML17095A41517 April 2017Request for Additional Information
NL-15-1055, License Amendment Request to Revise Technical Specification 3.4.14, RCS Pressure Isolation Valve Leakage to Eliminate the RHR Autoclosure Interlock Function from the Technical Specifications31 August 2015License Amendment Request to Revise Technical Specification 3.4.14, RCS Pressure Isolation Valve Leakage to Eliminate the RHR Autoclosure Interlock Function from the Technical Specifications
ML14308A04810 March 2015Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c)
ML14091A1501 April 2014Initial Exam 2013-301 Draft SRO Written Exam
NL-13-2039, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants30 October 2013Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5
ML14038A02424 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5
ML14038A02224 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5
ML14038A02124 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5
ML14038A02024 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5
IR 05000348/20130022 May 2013IR 05000348-13-002 and 05000364-13-002, 01/01/2013 - 03/31/2013; Joseph M. Farley Nuclear Plant, Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
ML12214A34723 July 2012Initial Exam 2012-301 Draft Sim IN-Plant Jpms
ML12214A47023 July 2012Initial Exam 2012-301 Final Sim-In-Plant JPMs
NL-12-0016, Response to NRC Request for Additional Information on License Amendment Request for Technical Specification Table 3.3.1.1 in Response to Westinghouse NSAL 09-01, Rod Withdrawal at Power3 February 2012Response to NRC Request for Additional Information on License Amendment Request for Technical Specification Table 3.3.1.1 in Response to Westinghouse NSAL 09-01, Rod Withdrawal at Power
NL-10-2355, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.05 January 2011Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.0
NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..29 October 2010License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..
IR 05000348/201000229 April 2010IR 05000348-10-002 and 05000364-10-002; 01/01/2010 - 03/31/2010; Joseph M. Farley Nuclear Plant, Units 1 and 2; Fire Protection Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications; and Event Follow-up
NL-09-0982, Response to Request for Additional Information Re NRC Generic Letter 2004-0227 July 2009Response to Request for Additional Information Re NRC Generic Letter 2004-02
ML0906201179 March 2009Request for Additional Information
IR 05000348/200801116 July 2008IR 05000348-08-011; 6/13/2008 - 6/26/2008 - Joseph M. Farley Nuclear Plant; Unit 1; Other Activities
NL-08-0961, Technical Specifications Amendment Request Engineered Safety Feature Room Coolers Request for Additional Information20 June 2008Technical Specifications Amendment Request Engineered Safety Feature Room Coolers Request for Additional Information
NL-08-0551, Final Supplemental Response to NRC Generic Letter 2004-0229 April 2008Final Supplemental Response to NRC Generic Letter 2004-02
NL-08-2173, Supplemental Response to NRC Generic Letter 2004-0228 February 2008Supplemental Response to NRC Generic Letter 2004-02
NL-07-0117, Technical Specifications Amendment Request Engineered Safety Feature Room Coolers5 June 2007Technical Specifications Amendment Request Engineered Safety Feature Room Coolers
IR 05000348/200600228 April 2006IR 05000348-06-002 and 05000364-06-002; 01/01/2006-03/31/2006; Joseph M. Farley Nuclear Plant, Units 1 & 2
ML0603703879 February 2006RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors
IR 05000348/200400722 June 2004IR 05000348-04-007 & 05000364-04-007, on 05/10/04 Through 05/14/04, for Southern Nuclear Operating Company, Inc., Columbia, AL
NL-04-0469, Response to RAI Related to DC Sources - Operating31 March 2004Response to RAI Related to DC Sources - Operating
ML04062067420 February 2004Revision 51 to FNP-0-EIP-9.0, Emergency Classification and Actions.
NL-03-1259, Risk-Informed Inservice Inspection Program - ASME Code Category B-F, B-J, C-F-1 & C-F-2 Piping17 July 2003Risk-Informed Inservice Inspection Program - ASME Code Category B-F, B-J, C-F-1 & C-F-2 Piping
ML0301506216 January 2003Transmittal of Latest Revision for Farley Emergency Plan Implementing Procedures 9.0 & 9.5
ML02338053627 November 2002Transmittal of RAI Responses for WCAP-15622, Risk-Informed Evaluation of Extensions to AC Electrical Power System Completion Times (MUHP-3010)
ML02333045727 November 2002Transmittal of RAI Responses for WCAP-15622, Risk-Informed Evaluation of Extensions to AC Electrical Power System Completion Times. (MUHP-3010)
L-02-000, Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension4 April 2002Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension
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