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Category:Calculation
MONTHYEARNL-17-0580, and Vogtle, Annual Non-Radioactive Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 20162017-04-26026 April 2017 and Vogtle, Annual Non-Radioactive Environmental Operating Reports, Annual Radioactive Effluent Release Reports, and Offsite Dose Calculation Manual for 2016 ML16314A5172016-11-0303 November 2016 Calculation SNC024-CALC-004, VEGP Determination of Emergency Action Level for Initiating Condition E-HU1. ML16314A5212016-11-0303 November 2016 Southern Nuclear Design Calculation X6CNA14 ML16260A1012016-09-22022 September 2016 Draft Fuel Handling Accident Dose Consequences Using AST Methods ML16260A1092016-09-22022 September 2016 Draft LOCA Dose Consequences Using AST Methods NL-16-0388, Draft Fuel Handling Accident Dose Consequences Using AST Methods2016-09-22022 September 2016 Draft Fuel Handling Accident Dose Consequences Using AST Methods NL-16-0388, Draft LOCA Dose Consequences Using AST Methods2016-09-22022 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-96-1064-0012016-07-25025 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 20152016-04-27027 April 2016 Annual Radioactive Effluent Release Reports and Offsite Dose Calculation Manual for 2015 NL-16-0007, Technical Specification 3.3.5, Loss of Power Diesel Generator Start Instrumentation, Supplement to License Amendment Request2016-01-12012 January 2016 Technical Specification 3.3.5, Loss of Power Diesel Generator Start Instrumentation, Supplement to License Amendment Request ML14038A0222013-09-24024 September 2013 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, Verion 1.0. Part 1 of 52013-09-24024 September 2013 Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5 NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 52013-09-24024 September 2013 Farley, 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 52013-09-24024 September 2013 Farley, 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 52013-09-24024 September 2013 Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5 ML14038A0202013-09-24024 September 2013 Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Verion 1.0. Part 1 of 5 ML14038A0212013-09-24024 September 2013 Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5 ML14038A0242013-09-24024 September 2013 Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5 ML14038A0252013-09-24024 September 2013 Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 5 of 5 ML13198A4632013-06-30030 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 ML14038A0272012-09-11011 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 22012-06-28028 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 ML14038A0302012-06-28028 June 2012 Calculations Number: PRA-BC-F-11-004, Fire PRA Logic Model for Farley Nuclear Plants, Version 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 22012-06-26026 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 ML14038A0312012-06-26026 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, Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 12011-09-15015 September 2011 Calculation Number; PRA-BC-F-11-006, Farley Fire PRA Task 13, Seismic-fire Interactions Assessment, Version 1 ML0712204732006-03-31031 March 2006 Offsite Dose Calculation Manual, Version 22 ML0612402532005-09-30030 September 2005 Offsite Dose Calculation Manual - Version 21 2017-04-26
[Table view] Category:Report
MONTHYEARNL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML21214A3182021-08-0202 August 2021 301 Comments NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic NL-20-0034, Inservice Inspection Program Owner'S Activity Report for Outage 1R292020-01-17017 January 2020 Inservice Inspection Program Owner'S Activity Report for Outage 1R29 NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 NL-19-0795, Cameron Non-Proprietary Engineering Reports; ER-1180NP, Rev. 1, ER-1181NP, Rev. 1; ER-1182NP, Rev. 1; and ER-1183NP, Rev. 1.2019-05-31031 May 2019 Cameron Non-Proprietary Engineering Reports; ER-1180NP, Rev. 1, ER-1181NP, Rev. 1; ER-1182NP, Rev. 1; and ER-1183NP, Rev. 1. NL-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure2018-04-0606 April 2018 Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure NL-17-2061, Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B2017-12-14014 December 2017 Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B NL-17-1401, Post Accident Monitoring Report for 8 Train RVLIS2017-08-10010 August 2017 Post Accident Monitoring Report for 8 Train RVLIS NL-16-2541, Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results2016-11-29029 November 2016 Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results NL-16-0810, Submittal of Post Accident Monitoring Report2016-06-0909 June 2016 Submittal of Post Accident Monitoring Report NL-16-0683, Special Report No. 2016-002-00, Alternate AC Source Out of Service2016-06-0202 June 2016 Special Report No. 2016-002-00, Alternate AC Source Out of Service NL-16-0751, Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C2016-05-23023 May 2016 Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C ML16103A5732016-04-21021 April 2016 Final ASP Analysis (LER 364-14-002) ML16103A5722016-04-21021 April 2016 Transmittal of Final Farley Nuclear Plant Unit 2, Accident Sequence Precursor Analysis ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report NL-15-2276, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20142015-12-23023 December 2015 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 NL-15-1489, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-12082015-08-17017 August 2015 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-1208 ML15226A2292015-07-31031 July 2015 PWR Vessel Internals Program Plan for Aging Management of Reactor Internals NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals2015-07-31031 July 2015 J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals ML15182A1752015-06-26026 June 2015 Completion of Required Action by NRC Order EA-12-051 Reliable Spent Fuel Pool Level Instrumentation ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis NL-15-0418, Revision 6, Pressure Temperature Limits Reports2015-03-0505 March 2015 Revision 6, Pressure Temperature Limits Reports NL-15-0080, Special Report 2015-001-002015-01-26026 January 2015 Special Report 2015-001-00 NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20132014-12-0808 December 2014 Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 NL-14-1109, Third Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Reliable Spent Fuel Pool Instrumentation (EA-12-051)2014-08-26026 August 2014 Third Six-Month Status Report of the Implementation of the Requirements of the Commission Order with Regard to Reliable Spent Fuel Pool Instrumentation (EA-12-051) ML14128A0832014-06-0303 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 ML14098A4752014-04-16016 April 2014 Unit 1 - Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14101A1192014-04-16016 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-0342, Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 392 of 562 Through 429 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 392 of 562 Through 429 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 543 of 562 Through Attachment 62014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 543 of 562 Through Attachment 6 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 351 of 562 Through 391 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 351 of 562 Through 391 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 313 of 562 Through 350 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 313 of 562 Through 350 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 430 of 562 Through 462 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 430 of 562 Through 462 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 57 of 217 Through 107 of 2172014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 57 of 217 Through 107 of 217 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 463 of 562 Through 500 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 463 of 562 Through 500 of 562 ML14051A7342014-02-20020 February 2014 Updated Seismic Recommendation 2.3 Walkdown Report NL-14-0249, Enclosure 1, Updated Seismic Recommendation 2.3 Walkdown Report, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 22014-02-20020 February 2014 Enclosure 1, Updated Seismic Recommendation 2.3 Walkdown Report, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 2 ML14071A0622014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 1 of 562 Through 46 of 562 ML14071A0632014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 107 of 217 Through Attachment 8 Through End ML14071A0642014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 47 of 562 Through 90 of 562 ML14071A0652014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 91 of 562 Through 125 of 562 ML14071A0662014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 126 of 562 Through 160 of 562 ML14071A0692014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 234 of 562 Through 272 of 562 ML14071A0702014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 273 of 562 Through 312 of 562 ML14071A0762014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 562 2024-06-14
[Table view] Category:Technical
MONTHYEARNL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 NL-19-0795, Cameron Non-Proprietary Engineering Reports; ER-1180NP, Rev. 1, ER-1181NP, Rev. 1; ER-1182NP, Rev. 1; and ER-1183NP, Rev. 1.2019-05-31031 May 2019 Cameron Non-Proprietary Engineering Reports; ER-1180NP, Rev. 1, ER-1181NP, Rev. 1; ER-1182NP, Rev. 1; and ER-1183NP, Rev. 1. NL-17-1401, Post Accident Monitoring Report for 8 Train RVLIS2017-08-10010 August 2017 Post Accident Monitoring Report for 8 Train RVLIS ML16103A5722016-04-21021 April 2016 Transmittal of Final Farley Nuclear Plant Unit 2, Accident Sequence Precursor Analysis ML16103A5732016-04-21021 April 2016 Final ASP Analysis (LER 364-14-002) ML15226A2292015-07-31031 July 2015 PWR Vessel Internals Program Plan for Aging Management of Reactor Internals NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals2015-07-31031 July 2015 J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals ML14098A4752014-04-16016 April 2014 Unit 1 - Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-0342, Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Units 1 and 2, Seismic Hazard and Screening Report for CEUS Sites NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 197 of 562 Through 233 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 197 of 562 Through 233 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 273 of 562 Through 312 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 273 of 562 Through 312 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 107 of 217 Through Attachment 8 Through End2014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 107 of 217 Through Attachment 8 Through End NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 1, Updated Seismic Recommendation 2.3 Walkdown Report, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachme2014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 1, Updated Seismic Recommendation 2.3 Walkdown Report, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment NL-14-0249, Joseph M. Farley Nuclear Plant, Unit 1 - Updated Seismic Recommendation 2.3 Walkdown Report2014-02-20020 February 2014 Joseph M. Farley Nuclear Plant, Unit 1 - Updated Seismic Recommendation 2.3 Walkdown Report NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 1 of 562 Through 46 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 1 of 562 Through 46 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 392 of 562 Through 429 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 392 of 562 Through 429 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 126 of 562 Through 160 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 126 of 562 Through 160 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 47 of 562 Through 90 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 47 of 562 Through 90 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 91 of 562 Through 125 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 91 of 562 Through 125 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 234 of 562 Through 272 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 234 of 562 Through 272 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 351 of 562 Through 391 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 351 of 562 Through 391 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 108 of 217 Through 161 of 2172014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 108 of 217 Through 161 of 217 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 57 of 217 Through 107 of 2172014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 57 of 217 Through 107 of 217 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 430 of 562 Through 462 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 430 of 562 Through 462 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 543 of 562 Through Attachment 62014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 543 of 562 Through Attachment 6 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 463 of 562 Through 500 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 463 of 562 Through 500 of 562 ML14071A0692014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 234 of 562 Through 272 of 562 ML14071A0812014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 162 of 217 Through 193 of 217 ML14071A0802014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 108 of 217 Through 161 of 217 ML14071A0792014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 57 of 217 Through 107 of 217 ML14071A0742014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 430 of 562 Through 462 of 562 ML14071A0772014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 543 of 562 Through Attachment 6 ML14071A0762014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 501 of 562 Through 542 of 562 ML14071A0752014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 463 of 562 Through 500 of 562 ML14071A0732014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 392 of 562 Through 429 of 562 ML14071A0722014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 351 of 562 Through 391 of 562 ML14071A0712014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 313 of 562 Through 350 of 562 ML14071A0702014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 273 of 562 Through 312 of 562 ML14071A0682014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 197 of 562 Through 233 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 161 of 562 Through 196 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 161 of 562 Through 196 of 562 ML14071A0672014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 161 of 562 Through 196 of 562 ML14071A0662014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 126 of 562 Through 160 of 562 ML14071A0652014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 91 of 562 Through 125 of 562 ML14071A0642014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 47 of 562 Through 90 of 562 ML14071A0632014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 7 Page 107 of 217 Through Attachment 8 Through End ML14071A0622014-02-20020 February 2014 Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 1 of 562 Through 46 of 562 NL-14-0249, Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 313 of 562 Through 350 of 5622014-02-20020 February 2014 Joseph M. Farley, Unit 1, Enclosure 2, Updated Farley Unit 1 Seismic Walkdown Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic Through Attachment 3 Page 313 of 562 Through 350 of 562 2022-07-14
[Table view] |
Text
Enclosure 6 to NL-13-1257 WORLD LEADER IN NUCLEAR AND CHEMICAL PROCESS SAFETY Report No.: FAlj13-0392 Request for Additional Information by the Office of Nuclear Reactor Regulation Joseph M. Farley Nuclear Plants, Units 1 and 2 Southern Nuclear Operating Company Docket Nos. 50-348 and 50-364 Revision 0 Project No.: SNC-WRAI-CST-Vortex Submitted to:
Southern Nuclear Company (Farley Nuclear Generating Station)
Dothan, Alabama Prepared by:
Robert E. Henry Reviewed by:
Damian D. SteJanczyk june, 2013 RO 1 6W070 83 STREET
- 8URR RIDGE, ILLINOIS 6 0 5 2 7 (877) FAUSKE 1 OR (630) 3 2 3 - 8 7 5 0
Enclosure 6 to NL-13-1257 FAIl13-0392 Page 2 0/19 Rev. 0 June. 2013 CALCULATION NOTE COVER SHEET SECTION TO BE COMPLETED BY AUTHOR(S):
Calc-Note Number: FAV13-0392 Revision Number: o Request for Additional Infonnation by the Office of Nuclear Reactor Regulation Joseph M.
Farley Nuclear Plants, Units 1 and 2 Southern Nuclear Operating Company Docket Nos. 50-348 Title: and 50-364 RAls Support for Farley for Vortex Project Number Project: Suppression Or Shop Order: SNC-WRAI-CST-Vortex The document is issued to provide support to RAIs in regards to vortex suppression work at Purpose: Farley.
~-----------------------------------------------------------
Results Summary: The document provides information to address NRC's RAIs_
References of Resulting Reports, Letters, or Memoranda (Optional)
Author(s):
Name (Print or Type) Signature: Completion Date:
Robert E. Henry J ,
SECTION TO BE COMPLETED BY VERIFIER(S):
Verifier(s):
Name (Print or Type) Signature: Completion Date:
__D_am
__i_an_D
__- _St_e_fan
__CZ-"y,-k___ '~~:b= d Independent Review or Method of Design Review D Alternate Calculations D Testing D Verification:
3-Pass Method ~ Other (specify): D SECTION TO BE COMPLETED BY MANAGER:
Responsible Manager:
Name (Print or Type) Signature: Approval Date:
Jens Conzen to NL-13-1257 FAI/13-0392 Page 3 of 19 Rev. 0 June, 2013 3-PASS VERIFICATION METHODOLOGY CHECKLIST 3-Pass Verification Review Topic Yes No N/A First Pass
- 1. Were the general theme, scope of document and scope of review
~? ~ D Second Pass
- 2. Do the references appear to be documented correctly? Is there enough information present to ensure the referenced document is ~ D retrievable?
- 3. Do the acceptance criteria seem appropriate?
D D
- 4. Does the technical content of the calculation note make sense from a qualitative standpoint and are appropriate methods used? ~ D Third Pass
- 5. Do the results and conclusions meet the acceptance criteria? Do the results and conclusions make sense and support the purpose of the ~ D calculation note?
- 6. Has the technical content of the document been verified in adequate detail? Examples of technical content include inputs, models, techniques, output, hand calculations, results, tables, plots, units of ~ D measure, etc.
- 7. Does the calculation note provide sufficient details in a concise manner? Note that sufficient detail is enough information such that a qualified person could understand the analysis and replicate the D results without consultation in the author.
- 8. Is the calculation note acceptable with respect to spelling, punctuation, and grammar? D
- 9. Are the references accurate? Do the references to other documents point to the latest revision? If not, are the reasons documented? Are ~
the references retrievable?
D D
- 10. Are computer code names spelled correctly? If applicable, are numerals included in the official code name as appropriate? D D
- 11. Has the calculation note been read word-for-word, cover-to-cover?
D to NL-13-1257 FAI/13-0392 Page 4 of 19 Rev. 0 June, 2013 EDITORIAL REVIEW CHECKLIST Reviewer Name: Damian D. Stefanczyk Date: June, 2013 Document Number: FAI/13-0392 Yes No N/A General Documents
- 1. Proofread the document for general format, readability, punctuation, and grammar. Are these acceptable to you?
- 2. Is the documentation legible, reproducible and in a form suitable for archiving as a Quality Record?
- 3. Are all the pages sequentially numbered and are the document number, revision number, and appropriate proprietary classification listed on each page?
- 4. Is the Record of Revision page filled in correctly including Revision, Date, and Description of Revisions, if applicable?
- 5. Are the page numbers in the Table of Contents provided and correct?
- 6. Are Acronyms defined in the document (either individually or on a separate page)?
- 7. Are Figures labeled consistently and do they include units of measure?
- 8. Are the units of measure clearly identified and used throughout?
- 9. Do all cross references to tables, figures, references, and sections point to an object of the given type?
- 10. Are symbols (e.g., Greek letters) used correctly?
- 11. Is sufficient information provided for all "References" to facilitate their retrieval including documents not maintained as quality records by Westinghouse, or has a copy been provided in an Appendix to the report?
- 12. Are all References listed referred to in the text?
- 13. Is the content of the Appendices consistent with what the document states it is?
Calc Notes Body of Calc Notes (Note that different Calc Note templates have different Section numbering. See the Section Numbering Key on last page for assistance.)
- 14. Is all information in the cover page header block completed appropriately?
- 15. Are the author and verifier applicable page numbers provided?
- 16. Is the report revision number on each page?
- 17. Are Tables labeled consistently and do they include units of measure?
- 18. Is background information and purpose of the calculation clearly stated in the appropriate section?
to NL-13-1257 FAI/13-0392 Page 5 of 19 Rev. 0 June, 2013 Yes No N/A
- 19. Have the limits of applicability been listed in the appropriate section?
- 20. Are open items identified in the appropriate section and on the cover page header block?
- 21. Are the Acceptance Criteria listed in the appropriate section (if applicable)?
- 22. Does the Calc Note include a discussion on the methodology used?
- 23. If applicable, are references to the utility, plant, unit, and cycle correct with respect to spelling and consistency of use?
Body of Document
- 24. Is the Summary of Results and Conclusions section consistent with the purpose stated and consistent with the results section?
Computer Runs
- 25. Are the computer codes used clearly identified in the appropriate section and is all required information included?
- 26. Are all electronic files listed in the electronically attached file listing?
- 27. Does the electronically attached file listing appropriately reference the codes used?
Checklists
- 28. Has the verifier initiated one or more of the Verification Methods of review in the Verification Method Checklist?
- 29. Has the verifier provided an explanation of the method of review in the Verification Method Checklist?
- 30. Is an explanation or justification for any "NO" responses on the 3-Pass Methodology Checklist(s) presented?
- 31. Are Author's responses provided to Additional Verifier Comments or noted as not required?
Additional Questions for Software Calc Notes
- 32. Is the software name, version number, and system state(s) where the software was created or validated provided?
- 33. Is a source code listing or reference to a controlled location of the source code included?
- 34. Do the test results include the date of execution and the machine name?
- 35. Do the test cases include a description of what is being tested?
Editorial Reviewer Comments (if needed):
to NL-13-1257 FAI/13-0392 Page 6 of 19 Rev. 0 June, 2013 RECORD OF REVISIONS Rev. Date Revision Description 0 June, 2013 Original issue.
This document is being issued as non-proprietary and is available for public release through the NRC.
to NL-13-1257 FAI/13-0392 Page 7 of 19 Rev. 0 June, 2013 TABLE OF CONTENTS CALCULATION NOTE COVER SHEET ..................................................................................2 3-PASS VERIFICATION METHODOLOGY CHECKLIST ......................................................3 EDITORIAL REVIEW CHECKLIST .........................................................................................4 RECORD OF REVISIONS .........................................................................................................6 LIST OF FIGURES ....................................................................................................................8 LIST OF ACRONYMS ...............................................................................................................9
1.0 BACKGROUND
/PURPOSE ............................................................................................ 10 2.0 RESPONSES TO RAIs FOR FARLEY CST TS VOLUME LAR ..................................... 11
3.0 REFERENCES
................................................................................................................. 19 to NL-13-1257 FAI/13-0392 Page 8 of 19 Rev. 0 June, 2013 LIST OF FIGURES Figure 2-1 Re-drawn figure showing the dimensions of the scaled test for D.C. Cook (Sanders et al., 2001)..........................................................................................12 Figure 2-2 FAI #1 flume test facility (side view) with a downward facing elbow (FAI, 2007).
..........................................................................................................................15 Figure 2-3 Example of ordinary Type 6 vortex (FAI, 2007). ................................................16 to NL-13-1257 FAI/13-0392 Page 9 of 19 Rev. 0 June, 2013 LIST OF ACRONYMS BWST Borated Water Storage Tank CST Condensate Storage Tank FAI Fauske & Associates, LLC FWST Fueling Water Storage Tank LAR License Amendment Request NRC Nuclear Regulatory Commission RAI Request for Additional Information RWST Refueling Water Storage Tank to NL-13-1257 FAI/13-0392 Page 10 of 19 Rev. 0 June, 2013
1.0 BACKGROUND
/PURPOSE Farley uses a vortex correlation developed by Harleman (1959) for a vertically downward configuration that differs from the 45 degree upward flow pipe used at Farley. This correlation is shown to over-predict the submergence by a factor of three when compared to Catawba and McGuire test data at the Froude number that corresponds to the maximum flow rate from the CST. This would be a sufficient margin to justify using the Harleman correlation to support the LAR if the test data were established to be applicable. Achieving this requires an acceptable description of the plant configurations, the test configurations, and the test data. Thus, it is necessary to provide a complete description of the tests and test results for each test used to substantiate determination of critical submergence that includes the following:
- 1. Drawing of the plant tank and the plant suction pipe within the tank that provides all relevant dimensions,
- 2. Drawing of the corresponding test configuration that provides all relevant dimensions,
- 3. Description of how quantitative air entrainment is determined during testing,
- 4. Description of conduct of the test that includes any observations, and
- 5. Summary of the test data such as a plot of critical submergence as a function of Froude number.
to NL-13-1257 FAI/13-0392 Page 11 of 19 Rev. 0 June, 2013 2.0 RESPONSES TO RAIs FOR FARLEY CST TS VOLUME LAR
- 1. Drawings of the plant tank and the plant suction pipe within the tank that provide all relevant dimensions are the following applicable Farley CST drawings:
U-161693 Version 2.0; Unit 1 CST General Plan, U-213481 Version 3.0; Unit 2 CST General Plan, U-161703 Version B; Unit 1 CST 8 inch Auxiliary Feed Pump Suction Nozzle, and U-213493 Version A; Unit 2 CST 8 inch Auxiliary Feed Pump Suction Nozzle.
- 2. Drawings of the corresponding test configuration that provide all relevant dimensions are as follows:
D.C. Cook simulation, RWST dimensions:
48 feet diameter, 32 feet high with a 24 inch diameter suction pipe.
The model was a 12 foot diameter and 6 feet high tank with a 5.73 inch horizontal suction pipe that was approximately 5.5 inches above the tank floor and approximately 1.75 feet of suction piping inside the tank. See Figure 2-1 that is re-drawn from the figure in the referenced paper which is difficult to read in the original reference (Sanders et al., 2001).
The scaled tests for D.C. Cook provide insights into whether important rotational flow conditions are generated as a result of the tank geometry, the drain down transient, etc. These results are compared to the Harleman correlation, on page 12 of the report (FAI, 2009), where the submergence is increased by one-half of the suction pipe diameter. The submergence in the D.C. Cook experiments was defined with respect to the inside bottom surface of the suction pipe, as noted in Figure 5b of (FAI, 2009). The chart in Figure 3 of (FAI, 2009) shows that the Harleman correlation agrees well with the results of the D.C. Cook tests. Based on the D.C.
Cook tests, the FAI report states that the Harleman correlation provides good agreement with the D.C. Cook data for critical submergence characterizing the onset of air entrainment for radial inflow process.
to NL-13-1257 FAII13-0392 Page 12 of 19 Rev. 0 June, 2013
~I*--------- 12' 0" ---------+1-1 Return Line & Perforated Plate Sparger Tube Flow Straightener 6' 0" 5 3/4" (actual 1.0. 5.730") I+--+! l ' 6 3/32" 7' 3 3/4"
_tart_'"
20130606-1REH Fauske & AslOCiates, LLC Figure 2-1 Re-drawn figure showing the dimensions of the scaled test for D. C. Cook (Sanders et al., 2001).
to NL-13-1257 FAI/13-0392 Page 13 of 19 Rev. 0 June, 2013 Figure 9 (Johansson et al., 2006) of the Catawba FWST scaled tank configuration is the type of configuration used for the CST at Farley. It has a suction port with a 45 degrees angled downward configuration that requires the suction flow to enter the pipe from below. Figure 4 (Johansson et al., 2006) provides the test configuration, as well as some of the essential tank and nozzle dimensions. (The tank diameter is not shown, but estimated to be approximately 40 feet in diameter based on the drawing scale of Figure 4). This downward oriented suction configuration acts to considerably suppress the potential for air intrusion as demonstrated in the main body of the FAI report (FAI, 2009) for a downward facing elbow which is part of a FAI investigation for Coopers CST (FAI, 2007). This information for the downward facing elbow in the Cooper tests demonstrated that the water level had to be very close to the bottom of the elbow before gas intrusion would occur.
- 3. Description of how quantitative air entrainment is determined during testing is described as follows:
The FAI report (FAI, 2009) does not exactly identify the method in which the quantity of air entrainment is determined in the experiments. The following is related information provided in addition to the FAI report that best describes or discusses air entrainment:
Upon reviewing the referenced paper documenting the D.C. Cook experiments (Sanders et al., 2001), it was observed that a rectangular Plexiglas box was built on the transparent downcomer piping. This box was filled with water to compensate for the pipes curvature. The flow through this region was video recorded to capture when a continuous stream of air bubbles was detected in each test. In addition, the point at which the gas flow was estimated to occupy 2% of the downcomer volume was also noted. A similar technique was used to observe the onset of gas intrusion in the McQuire and Catawaba tests.
Figure 3 of the FAI report (FAI, 2009) shows the results of air intrusion as Critical Submergence versus Froude number. Results show that there is not much difference in the two methods: visual detection of a continuous stream of bubbles and visual estimate that the gas volume fraction in the downcomer pipe is equal to 2%.
A similar technique of constructing a rectangular box around the outlet pipe and filling the box with water was used to observe the onset of gas intrusion in the McQuire and Catawaba tests.
to NL-13-1257 FAI/13-0392 Page 14 of 19 Rev. 0 June, 2013 In the Cooper experiments performed at FAI (FAI, 2007), the tests were performed in a long rectangular flume with the water added at one end and the suction oriented at the other end as illustrated in Figure 2-2. This transparent configuration enabled the vortex behavior to be observed directly. The tests included formation of very tight Type 6 vortices (Figure 2-3) that were so small that they did not cause any degradation in the pump performance. In these experiments, it is conservative to assume that the air pulled in by the vortex is traveling at the same average velocity as the water. With this no slip assumption, it follows that a vortex transporting a 1% void fraction would have a diameter that is 10% of the suction pipe diameter:
2 D vortex D2
= 4 = vortex 2
D pipe D 2pipe 4
1% = 0.01 D 2vortex 0.01
D 2pipe D2vortex = 0.01 D 2pipe D vortex = 0.1 D pipe D vortex = 10% of Dpipe D vortex = diameter of vortex, D pipe = inner suction pipe diameter, and = area void fraction.
For the 4 inch suction pipe used in these tests, the vortex diameter would have to be more than about 3/8. From the stainless steel scale shown in Figure 2-3, the figure, the vortex diameter is much smaller that this which explains why the pump discharge flow rate was not degraded by the vortex.
When air flow intrusion begins at a submergence consistent with radial inflow, this shows that the air intrusion is not due to a vortex generated through rotational flow. Air intrusion consistent with radial inflow has nothing to do with rotational flows, i.e. vortex behavior. If rotational flow in the tank produced a vortex, then air intrusion would occur at a higher water level than that calculated by radial inflow.
The Harleman et al. correlation (Harleman et al., 1959) and the Lubin-Springer correlation (Lubin/Springer, 1967) can be viewed as defining (bounding) the to NL-13-1257 FAI/13-0392 Page 15 of 19 Rev. 0 June, 2013 minimum submergence that would prevent air intrusion in the absence of rotational flows that induce vortex formation. In this regard, the Harleman correlation is conservative for defining the minimum submergence level where air intrusion would be expected to occur.
Figure 2-2 FAI #1 flume test facility (side view) with a downward facing elbow (FAI, 2007).
to NL-13-1257 FAI/13-0392 Page 16 of 19 Rev. 0 June, 2013
' - - - - -I Type 6 Figure 2-3 Example of ordinary Type 6 vortex (FAI, 2007).
to NL-13-1257 FAI/13-0392 Page 17 of 19 Rev. 0 June, 2013 As noted in Section 3 of (FAI, 2009), the Oconee tests performed by Alden Labs for Duke Power (Johansson et al., 2006) were performed in two ways: with and without recirculation to the simulated BWST. This is important for the assessment of vortex formation in the transient, because the outflow consumes much of the turbulence/swirl that is trying to organize into a vortex. As noted in Section 2 of (Knauss, 1987): Once a vortex is reduced in strength or dissipated, such as by wall friction, it takes some time for the flow to reorganize and produce enough circulation for the vortex to reform. Examining the Oconee tests, it is noted that tests with no flow return to the tank have lower submergence levels than those with return flow to the tank. The same behavior is observed in numerous FAI tests that have been performed for various tanks for different reactor sites. Specifically, recirculating all of the suction to the tank is a very conservative representation of the flow field since it provides a steady-state source to eventually organize into a swirl and the level remains constant as this happens. Representing the drain-down behavior results in water levels that are in a region bounded by the Harleman and Lubin-Springer radial inflow correlations.
- 4. Description of conduct of the test that includes any observations, and See the expanded discussion given above in point 3.
- 5. Summary of the test data such as a plot of critical submergence as a function of Froude number:
Figure 3 of (FAI, 2009) is a plot of the reported test data for the onset of air intrusion and the conditions that resulted in an estimate void fraction of 2%.
These data points are represented in terms of dimensionless water submergence as a function of the Froude Number. As discussed in point 1, the D.C. Cook tests are a representation of air intrusion (open loop) and steady state (closed loop) modes in which the water level, at a given flow rate, was decreased until air intrusion into the horizontal pipe was observed.
Figure 3 of (FAI, 2009) also plots the Harleman et al. and Lubin-Springer correlations to compare to the experimental data from the D.C. Cook tests. The Lubin-Springer correlation somewhat underestimates the critical submergence observed in the D.C. Cook tests. However, the Harleman et al. correlation is in good agreement with the data for the critical submergence characterizing the onset of air entrainment. The Harleman et al. correlation for horizontal suction pipe is described in the second equation on Page 13 of 25 of (FAI, 2009). As noted earlier, the 0.5 is added because the submergences reported for the scaled D.C. Cook RWST are with respect to the inner bottom surface of the discharge pipe.
to NL-13-1257 FAI/13-0392 Page 18 of 19 Rev. 0 June, 2013 Figure 6 of (FAI, 2009) plots data which represents the test results of the scaled Oconee BWST during a drain-down transient. The figure compares the onset of air entrainment test results for the no recirculation configuration with the two radial inflow correlations, Harleman et al. and Lubin-Springer. The Oconee BWST is configured with a horizontal suction pipe that is flush mounted onto the side of the tank. The difference between these tests and the D.C. Cook tests is that submergence defined as the water depth with respect to the centerline of the suction pipe. The pipe had a smaller inner diameter which resulted in Froude numbers from one to four. Here again, the Harleman et al. correlation applied to the horizontal suction pipe for tests in which the drain-down is represented is in good agreement with the data and bounds the test results.
Figure 8 of (FAI, 2009) plots data taken from the McGuire and Catawba scaled experiments (Johansson et al., 2006). This figure compares steady-state and transient (drain-down) data taken with downward facing elbow suction nozzles as illustrated in Figure 7 of (Johansson et al., 2006). This is the suction configuration used for the Farley CSTs. In addition to the test results, this figure shows a bounding correlation developed for air intrusion into the downward facing suction configuration for the CST at Cooper. This correlation is presented on Page 21 of 25 of (FAI, 2009). It is seen that the test data developed in the McGuire and Catawba experiments are in good agreement with that developed in the Cooper CST experiments. Note that, like the test data discussed above for the Oconee BWST, the transient (drain-down) test data result in lower submergence water levels than the steady-state data. Also, once the Froude number becomes less than 0.5, gas can begin to accumulate in the discharge piping as was observed for the D.C. Cook tests. With this background, the FAI report (FAI, 2009) concludes that the McGuire and Catawba scaled experiments provide a significant technical basis for assessing both the Farley and Vogtle RWST behaviors. Since the Farley CSTs have the same downward facing suction configuration, this conclusion can also be applied to the Farley CSTs.
to NL-13-1257 FAI/13-0392 Page 19 of 19 Rev. 0 June, 2013
3.0 REFERENCES
FAI. (2007). "Test Results for Possible Vortex Induced Air Intrusion in the Cooper ECST Suction Flow". FAI/07-121: Fauske & Associates, LLC.
FAI. (2009). "Vortex Evaluation for Vogtle and Farley RWSTs and Hatch CSTs". FAI/09-19:
Fauske & Associates, LLC.
Harleman et al. (1959). "Selective Withdrawal from a Vertically Stratified Fluid". 8th Congress, Montreal, August 24-29: International Association for Hydraulic Research.
Johansson et al. (2006). Hydraulic Model Study of Refueling Water Storage Tank and Borated Water Storage Tank to Evaluate the Formation of Air Drawing Vortices and Air Withdrawal for McGuire, Catawba and Oconee Nuclear Power Stations. Alden Research Laboratory Report 2006-314_H949C to Duke Energy Corporation.
Knauss, J. (1987). "Swirling Flow Problems at Intakes". Roterdam: Hydraulic Structures Design Manual, A. A. Balkema.
Lubin/Springer. (1967). The Formation of a Dip on the Surface of a Liquid Draining from a Tank. Journal of Fluid Mechanics, 29, pp. 385-390.
Sanders et al. (2001). Air Entrainment in a Partially Filled Horizontal Pump Suction Line.
New Orleans, La., Paper JPGC2001/PWR-19010, pp 95-103: Proceedings of the JPGC-01, 2001 International Joint Power Generation Conference.