Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
NL-19-0009, Supplemental Response to Alternative Request HNP-ISI-ALT-05-048 January 2019Supplemental 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 201626 April 2017and Vogtle, Annual Non-Radioactive Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 2016Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Grace period
Power change
ML16314A5173 November 2016Calculation SNC024-CALC-004, VEGP Determination of Emergency Action Level for Initiating Condition E-HU1.
ML16314A5213 November 2016Southern Nuclear Design Calculation X6CNA14Surveillance Frequency Control Program
Pressure Boundary Leakage
Power change
ML16260A10922 September 2016Draft LOCA Dose Consequences Using AST Methods
ML16260A10122 September 2016Draft Fuel Handling Accident Dose Consequences Using AST Methods
NL-16-0388, Draft Fuel Handling Accident Dose Consequences Using AST Methods22 September 2016Draft Fuel Handling Accident Dose Consequences Using AST Methods
NL-16-0388, Draft LOCA Dose Consequences Using AST Methods22 September 2016Draft 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-96-1064-00125 July 2016Units 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 201527 April 2016Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manual for 2015Offsite 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 Request12 January 2016Technical 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 Assembly13 August 2015Attachment 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 EFPY10 September 2014Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPYShutdown Margin
Hydrostatic
ML15322A09210 September 2014Calculation No. 1001527.304, Revision 2, Hatch Unit 1, P-T Curve Calculation for 38 and 49.3 EFPYShutdown Margin
Hydrostatic
NL-15-2034, Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPY10 September 2014Calculation No. 1001527.305, Revision 2, Hatch Unit 2 P-T Curve Calculation for 37 and 50.1 EFPYShutdown 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 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5Hot 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 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5Hot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Mission time
Fire Barrier
Probabilistic Risk Assessment
Large early release frequency
ML14038A02524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 5 of 5
ML14038A02424 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5Hot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Mission time
Fire Barrier
Probabilistic Risk Assessment
Large early release frequency
ML14038A02224 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5Hot Short
Safe Shutdown
Mission time
Fire Barrier
Probabilistic Risk Assessment
Large early release frequency
ML14038A02124 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5Hot Short
Safe Shutdown
Shutdown Margin
Mission time
Fire Barrier
Probabilistic Risk Assessment
Large early release frequency
ML14038A02024 September 2013Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5Hot 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 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 3 of 5Hot 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 524 September 2013Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5Hot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Mission time
Fire Barrier
Probabilistic Risk Assessment
Operator Manual Action
Large early release frequency
Fire Protection Program
ML13198A46330 June 2013FAI/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
ML14125A10128 February 2013Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23Offsite Dose Calculation Manual
NL-14-0659, Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 2928 February 2013Enclosure 5: Vogtle Offsite Dose Calculation Manual - Version 29Grab 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 2328 February 2013Enclosure 4: Hatch Offsite Dose Calculation Manual - Version 23Offsite Dose Calculation Manual
ML14038A02711 September 2012Joseph 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 228 June 2012Joseph M. Farley, Units 1 and 2, Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2
ML14038A03028 June 2012Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 2
ML14038A03126 June 2012Joesph 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 226 June 2012Joesph 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 2012Response 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 Development30 December 2011Calculation 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 DevelopmentFinite Element Analysis
ML15322A09130 December 2011Calculation 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 DevelopmentFinite Element Analysis
NL-13-1503, Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 115 September 2011Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 1Safe Shutdown
Fire Barrier
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Earthquake
Fire Protection Program
ML12122A14528 February 2011Enclosure 4 - Vogtle Offsite Dose Calculation Manual - Version 28Grab 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. 22 May 2008Transmittal of Analytical Evaluation of Flaws, Calculation No. 0800236.00-301, Rev. 2Finite Element Analysis
ML07122047230 November 2006Offsite Dose Calculation Manual, Version 19Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power change
ML07122047331 March 2006Offsite Dose Calculation Manual, Version 22Grab sample
Offsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
Process Control Program
Power change
NL-06-0422, Evaluation of Main Steam Nozzle Indications1 March 2006Evaluation of Main Steam Nozzle Indications
ML07324057325 January 2006Calculation 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-4002Environmental Justice
ML06124025031 October 2005Offsite Dose Calculation Manual - Version 16Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power change
ML06124025330 September 2005Offsite Dose Calculation Manual - Version 21Grab 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 Welds30 January 2004Fluence Calculations and Methodology for the Unit I Updated Analysis of Core Shroud Vertical Welds
ML06100054427 March 2002Offsite Dose Calculation Manual (ODCM) Implementation and Control Procedure Number 36010-C Rev 11.2Offsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
ML07171008127 September 1985Calculation G-008, Vogtle Nuclear Power Plant, Flow Rate in Mathes Pond Stream & West Branch Stream.
ML0717100733 May 19728.7.1 Aquifer Tests for Construction Dewatering