NL-19-0009, Supplemental Response to Alternative Request HNP-ISI-ALT-05-04 | 8 January 2019 | Supplemental Response to Alternative Request HNP-ISI-ALT-05-04 | |
NL-17-0580, and Vogtle, Annual Non-Radioactive Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 2016 | 26 April 2017 | and Vogtle, Annual Non-Radioactive Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 2016 | Grab sample Offsite Dose Calculation Manual Met Tower Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Grace period Power change |
ML16314A517 | 3 November 2016 | Calculation SNC024-CALC-004, VEGP Determination of Emergency Action Level for Initiating Condition E-HU1. | |
ML16314A521 | 3 November 2016 | Southern Nuclear Design Calculation X6CNA14 | Surveillance Frequency Control Program Pressure Boundary Leakage Power change |
ML16260A109 | 22 September 2016 | Draft LOCA Dose Consequences Using AST Methods | |
ML16260A101 | 22 September 2016 | Draft Fuel Handling Accident Dose Consequences Using AST Methods | |
NL-16-0388, Draft Fuel Handling Accident Dose Consequences Using AST Methods | 22 September 2016 | Draft Fuel Handling Accident Dose Consequences Using AST Methods | |
NL-16-0388, Draft LOCA Dose Consequences Using AST Methods | 22 September 2016 | Draft LOCA Dose Consequences Using AST Methods | |
NL-16-0784, Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-001 | 25 July 2016 | Units 1 and 2 - Response to Request for Additional Information for TSTF-312. Enclosure 2 Excerpts from Calculation SM-96-1064-001 | |
NL-16-0644, Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manual for 2015 | 27 April 2016 | Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manual for 2015 | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report |
NL-16-0007, Technical Specification 3.3.5, Loss of Power Diesel Generator Start Instrumentation, Supplement to License Amendment Request | 12 January 2016 | Technical Specification 3.3.5, Loss of Power Diesel Generator Start Instrumentation, Supplement to License Amendment Request | |
NL-15-1904, Attachment F of Enclosure 2, Calculation No. ALION-CAL-SNC-7410-005, Revision 1, Head Loss Testing of a Prototypical Vogtle 1 and 2 Strainer Assembly | 13 August 2015 | Attachment F of Enclosure 2, Calculation No. ALION-CAL-SNC-7410-005, Revision 1, Head Loss Testing of a Prototypical Vogtle 1 and 2 Strainer Assembly | |
NL-15-2034, Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPY | 10 September 2014 | Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPY | Shutdown Margin Hydrostatic |
ML15322A092 | 10 September 2014 | Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPY | Shutdown Margin Hydrostatic |
NL-15-2034, Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY | 10 September 2014 | Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY | Shutdown Margin Hydrostatic Finite Element Analysis Pressure and Temperature Limits Report |
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5 | 24 September 2013 | Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5 | Hot Short Safe Shutdown Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5 | 24 September 2013 | Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5 | Hot Short Safe Shutdown Boric Acid Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
ML14038A025 | 24 September 2013 | Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 5 of 5 | |
ML14038A024 | 24 September 2013 | Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5 | Hot Short Safe Shutdown Boric Acid Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
ML14038A022 | 24 September 2013 | Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5 | Hot Short Safe Shutdown Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
ML14038A021 | 24 September 2013 | Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5 | Hot Short Safe Shutdown Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
ML14038A020 | 24 September 2013 | Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5 | Hot Short Safe Shutdown Boric Acid Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Operator Manual Action Large early release frequency Fire Protection Program |
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5 | 24 September 2013 | Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5 | Hot Short Safe Shutdown Mission time Fire Barrier Probabilistic Risk Assessment Large early release frequency |
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5 | 24 September 2013 | Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5 | Hot Short Safe Shutdown Boric Acid Shutdown Margin Mission time Fire Barrier Probabilistic Risk Assessment Operator Manual Action Large early release frequency Fire Protection Program |
ML13198A463 | 30 June 2013 | FAI/13-0392 - Request for Additional Information by the Office of Nuclear Reactor Regulation Joseph M. Farley Nuclear Plants, Units 1 and 2 Southern Nuclear Operating Company, Project No.: SNC-WRAI-CST-Vortex | |
ML14125A101 | 28 February 2013 | Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23 | Offsite Dose Calculation Manual |
NL-14-0659, Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29 | 28 February 2013 | Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29 | Grab sample Offsite Dose Calculation Manual Met Tower Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
NL-14-0659, Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23 | 28 February 2013 | Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23 | Offsite Dose Calculation Manual |
ML14038A027 | 11 September 2012 | Joseph M. Farley, Units 1 and 2, Calculation Number: PRA-BC-F-11-014, Fire Scenario Development, Version 2 | |
NL-13-1503, Joseph M. Farley, Units 1 and 2, Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2 | 28 June 2012 | Joseph M. Farley, Units 1 and 2, Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2 | |
ML14038A030 | 28 June 2012 | Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2 | |
ML14038A031 | 26 June 2012 | Joesph M. Farley, Units 1 and 2, Calculation Number: PRA-BC-F-11-002, Component Selection for Farley Fire PRA, Version 3. Part 1 of 2 | |
NL-13-1503, Joesph M. Farley, Units 1 and 2, Calculation Number: PRA-BC-F-11-002, Component Selection for Farley Fire PRA, Version 3. Part 1 of 2 | 26 June 2012 | Joesph M. Farley, Units 1 and 2, Calculation Number: PRA-BC-F-11-002, Component Selection for Farley Fire PRA, Version 3. Part 1 of 2 | |
NL-12-0872, Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.7.9 Ultimate Heat Sink (UHS) | 30 April 2012 | Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.7.9 Ultimate Heat Sink (UHS) | Ultimate heat sink |
NL-15-2034, Calculation No. 1001527.303, Revision 0, Feedwater, Water Level Instrument, and Core Dp Nozzle Fracture Mechanics Evaluation for Hatch, Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development | 30 December 2011 | Calculation No. 1001527.303, Revision 0, Feedwater, Water Level Instrument, and Core Dp Nozzle Fracture Mechanics Evaluation for Hatch, Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development | Finite Element Analysis |
ML15322A091 | 30 December 2011 | Calculation No. 1001527.303, Revision 0, Feedwater, Water Level Instrument, and Core Dp Nozzle Fracture Mechanics Evaluation for Hatch, Unit 1 and Unit 2 Pressure-Temperature Limit Curve Development | Finite Element Analysis |
NL-13-1503, Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 1 | 15 September 2011 | Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 1 | Safe Shutdown Fire Barrier Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Earthquake Fire Protection Program |
ML12122A145 | 28 February 2011 | Enclosure 4 - Vogtle Offsite Dose Calculation Manual - Version 28 | Grab sample Offsite Dose Calculation Manual Met Tower Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
NL-08-0533, Transmittal of Analytical Evaluation of Flaws, Calculation No. 0800236.00-301, Rev. 2 | 2 May 2008 | Transmittal of Analytical Evaluation of Flaws, Calculation No. 0800236.00-301, Rev. 2 | Finite Element Analysis |
ML071220472 | 30 November 2006 | Offsite Dose Calculation Manual, Version 19 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML071220473 | 31 March 2006 | Offsite Dose Calculation Manual, Version 22 | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
NL-06-0422, Evaluation of Main Steam Nozzle Indications | 1 March 2006 | Evaluation of Main Steam Nozzle Indications | |
ML073240573 | 25 January 2006 | Calculation Package for Population Density and Environmental Justice Included in Er Section 2.3.1 Demography, 2.5.4 Environmental Justice, and 7.2 Severe Accidents, AR01-ER-XNC-4002 | Environmental Justice |
ML061240250 | 31 October 2005 | Offsite Dose Calculation Manual - Version 16 | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML061240253 | 30 September 2005 | Offsite Dose Calculation Manual - Version 21 | Grab sample Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program Power change |
NL-04-0073, Fluence Calculations and Methodology for the Unit I Updated Analysis of Core Shroud Vertical Welds | 30 January 2004 | Fluence Calculations and Methodology for the Unit I Updated Analysis of Core Shroud Vertical Welds | |
ML061000544 | 27 March 2002 | Offsite Dose Calculation Manual (ODCM) Implementation and Control Procedure Number 36010-C Rev 11.2 | Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report |
ML071710081 | 27 September 1985 | Calculation G-008, Vogtle Nuclear Power Plant, Flow Rate in Mathes Pond Stream & West Branch Stream. | |
ML071710073 | 3 May 1972 | 8.7.1 Aquifer Tests for Construction Dewatering | |