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Category:Letter type:NL
MONTHYEARNL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-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 NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, 2024-07-03
[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 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 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) 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 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 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 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 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 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:Miscellaneous
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 ML21214A3182021-08-0202 August 2021 301 Comments 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-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-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 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 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 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-14-0145, Proposed Alternative for the Fourth Lnterval Lnservice Inspection (FNP-ISI-ALT-14, Version 1.0)2014-02-18018 February 2014 Proposed Alternative for the Fourth Lnterval Lnservice Inspection (FNP-ISI-ALT-14, Version 1.0) NL-13-1936, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2013-09-30030 September 2013 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B NL-13-0954, Proposed Path to Closure of Generic Safety Issue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance.2013-05-16016 May 2013 Proposed Path to Closure of Generic Safety Issue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance. NL-13-0171, Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation.2013-02-27027 February 2013 Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation. ML12355A7852012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 284 of 561 - Page 330 of 561 ML13004A2632012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4, Page 130 of 143 Through End ML13004A2622012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4, Page 64 of 143 Through Page 129 of 143 NL-12-2266, Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover - Attachment 3: Seismic Walkdown Checklists, Page 58 of 5612012-11-26026 November 2012 Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover - Attachment 3: Seismic Walkdown Checklists, Page 58 of 561 NL-12-2266, Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 59 of 561 - Page 12012-11-26026 November 2012 Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 59 of 561 - Page 103 NL-12-2266, Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 1 of 161 - Page2012-11-26026 November 2012 Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 1 of 161 - Page 7 NL-12-2266, Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 71 of 161 - Pag2012-11-26026 November 2012 Joseph M. Farley, Unit 1, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 71 of 161 - Page ML13004A2612012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3, Page 431 of 467 Through Attachment 4, Page 63 of 143 ML13004A2602012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3, Page 373 of 467 Through Attachment 3, Page 431 of 467 NL-12-2266, SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover - Attachment 3: Seismic Walkdown Checklists, Page 58 of 5612012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover - Attachment 3: Seismic Walkdown Checklists, Page 58 of 561 ML12355A7802012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 59 of 561 - Page 103 of 561 ML12355A7812012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 104 of 561 - Page 140 of 561 ML12355A7822012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 141 of 561 - Page 183 of 561 ML12355A7832012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 184 of 561 - Page 233 of 561 ML12355A7842012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 234 of 561 - Page 283 of 561 ML13004A2582012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3, Page 307 of 467 Through Attachment 3, Page 372 of 467 ML12355A7862012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 331 of 561 - Page 373 of 561 ML12355A7872012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 374 of 561 - Page 415 of 561 ML12355A7882012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 416 of 561 - Page 444 of 561 ML12355A7892012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 445 of 561 - Page 482 of 561 ML12355A7902012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 483 of 561 - Page 533 of 561 ML12355A7912012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 3: Seismic Walkdown Checklists, Page 534 of 561 - Page 561 of 561 ML12355A7932012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 1 of 161 - Page 70 of 161 ML12355A7942012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 71 of 161 - Page 117 of 161 ML12355A7952012-11-26026 November 2012 SNCF164-RPT-01, Version 1.0, Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Attachment 4: Unit 1-Area Walk-by Checklists, Page 118 of 161 - End NL-12-2267, SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 46 of 462012-11-26026 November 2012 SNCF164-RPT-02, Ver. 1.0, Farley Unit 2 Seismic Walkdown Report, Rer SNC432467 for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 46 of 46 2024-06-14
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B. L. " Pete" Ivey Southern Nuclear Vi ce President Operating Company, Inc. Regul a tory Affairs 40 Inverness Center Parkway Post Off ic e Box 1295 Birmi ngh am, A L 35242 Te l 205.992.7619 Fax 205.992.521 7 February 27,2013 Docket 50-348 NL-13-0171 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant -Units 1 and Southern Nuclear Operating Company's Overall Integrated Plan In Response March 12,2012 Commission Order Modifying Licenses with Regard Requirements for Reliable Spent Fuel Pool Instrumentation (Order
References:
NRC Order Number EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated March 12,2012 NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-0S1, Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation, Revision 0, dated August 29, 2012 NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-0S1, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated August 24,2012 Southern Nuclear Operating Company letter NL-12-2150 to the NRC, Joseph M. Farley Nuclear Plant -Units 1 and 2 Southern Nuclear Operating Company's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-0S1), dated October 23, 2012 Ladies and Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission
("N RC" or "Commission")
issued an order (Reference
- 1) to Southern Nuclear Operating Company (SNC). Reference 1 was immediately effective and directs SNC to have Nuclear Regulatory Commission NL-13-0171 Page 2 a reliable indication of the water level in spent fuel pools. requirements are outlined in Attachment 2 of Reference
- 1. Reference 1 submission of an Overall Integrated Plan by February 2013. The NRC Interim Staff (ISG) (Reference
- 2) was issued August 29,2012 which endorses industry guidance document 12-02, 1 3) with clarifications and exceptions identified in 2. i-40TOr,Qnr'o 3 provides regarding content of this Reference 4 provided Joseph M. Nuclear (FNP) initial status report regarding spent instrumentation, as required by Reference
- 1. The purpose of this letter is to provide the Integrated Plan for FNP pursuant to Section IV, Condition C.1,
- 1. This confirms SNC received 2 and has an Integrated for FNP in accordance with the guidance for purpose of ensuring a reliable indication of the water in associated fuel storage capable of supporting identification of required wide pool water conditions by trained personnel.
information in the Enclosure the FNP Units 1 and 2 Overall Integrated Plan for reliable spent fuel pool instrumentation pursuant to Reference
- 3. The Integrated Plan is based on design information.
Final design and procedure as well as any to the information contained in Enclosure, will provided in the Integrated updates by Reference 1 SNC to fully implement the requirements of Order by breaker of the Unit 1 Spring 2015 refueling outage and the Unit 2 Fall 2014 outage Section IV, Condition A.2 of 1. In accordance with Section IV, Condition C.3 of 1, SNC intends to submit notification to the NRC that full compliance Order has been achieved within 60 of full implementation unit at FNP. This contains no new regulatory commitments.
If you have any contact Ken McElroy at (205) 992-7369.
U.S. Nuclear Regulatory Commission NL-13-0171 Page 3 Respectfully submitted, B. L. Ivey Vice President
-Regulatory Affairs BLl/CLN Mr. B. L. Ivey states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and , to the best of his knowledge and belief , the facts set forth in this letter are true. Sworn to and subscribed before me this ;L 7 tL day of , 2013. otary Pubflc My commission expires:1!,VA JJ 1 ,
Joseph M. Farley Nuclear Plant Units 1 and 2 Integrated Plan with Regard to Reliable Spent Fuel Pool Instrumentation Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President
& CEO Mr. D. G. Bost, Executive Vice President
& Chief I\luclear Officer Mr. T. A. Lynch, Vice President
-Farley Mr. B. J. Adams, Vice President
-Fleet Operations Mr. C. R. Pierce, Director -Regulatory Affairs RTYPE: CFA04.054 U. S. Nuclear Regulatorv Commission Mr. E. Leeds, Director of the Office of Nuclear Reactor Regulation Mr. V. M. McCree , Regional Administrator Ms. E. A. Brown, NRR Project Manager -Farley Mr. P. K. Niebaum, Senior Resident -Farley Mr. J. R. Sowa, Senior Resident -Farley Mr. Blake A. Purnell , NRRlJLD/PMB, NRC Mr. Steven R. Jones , NRR/DSS/SBPB, NRC Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer Joseph M. Farley Nuclear Plant -Units 1 and Southern Nuclear Operating Company's Overall Integrated Plan Response to March 12, 2012 Commission Order Modifying Licenses Regard to Requirements for Reliable Spent Fuel Pool (Order Joseph M. Farley Nuclear Plant Units 1 and 2 Integrated Plan with Regard Reliable Spent Fuel Pool Southern Nuclear Operating J. M. Farley Nuclear Units 1 & Reliable Spent Fuel Pool Overall Integrated Implementation Revision 0, February 27, 2013 FNP 1 & 2 RSFPI Integrated Plan Page 1 of 16 2/27/2013 12:19 PM T able of Con tents I. Introduction
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.. II. Schedule ..................................................................................................................... III. Identification of Spent Fuel Pool Water Levels ..........
....................................................... IV. Instruments
.. .... ........................................................................................................... V. Reliability
..................................................................................................................... VI. Instrument Channel Design Criteria ........................
........................................................ A. Arrangement
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.................................... B. Mounting............. ............................................
...... ...........................................................
....... .... C. Qualification
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................... ....... D. Independence
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... .. ....... .. ....... .. ..........
.... .... E. Power Supplies ............................................................
................................................................ F. Accuracy .......................................................................
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....... G. Testing ........................ ..............................
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...... H. Display.............
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............ .................... ....... VII. Instrument Channel Program Criteria ........................................................................... A. Training ..........................................
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.. B. Procedures
........................................................................... .................................................. ... C. Testing and Calibration
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...................... VIII. Need for Relief and Basis ........................................................................................
.... IX. References
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................................................... Attachment 1: Probe Location Sketch ...................................................................................... Attachment 2: Electrical Sketches ........................................
................................................... FNP 1 & 2 RSFPI Integrated Plan Page 2 of 16 2/27/2013 12:19 PM I.
The Nuclear Commission (NRC) EA-12-0S1, Issuance Order ta Modify Licenses with Regard to Reliable Spent Fuel Poo/lnstrumentation, 1) on March The Order licensees to have indication of water level in associated storage capable of identification the following water level conditions by trained personnel:
(1) that is adequate to support operation of the normal fuel pool cooling system, (2) level that is adequate to provide substantial radiation sh for a person on the pool deck, and (3) fuel remains covered and actions to implement make-up water addition should no longer be The also requires I of an overall integrated plan which will provide a of the the Order will achieved.
NEll2-02, Industry Guidance for Compliance with NRC fA-12-0S1, Modify Licenses with to Reliable Spent Fuel Poo/lnstrumentation," (Reference
- 4) provides an approach for with order EA-12-0S1.
NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order fA-12-0S1, Reliable Spent Fuel Instrumentation, (Reference
- 3) that methodologies and guidance in conformance with guidelines provided in NEI12-02, Revision 1, to the clarifications and exceptions specific to NEI 12-02 Section 3.4, means of requirements EA-l2-0S1.
This plan provides the Joseph M. Farley Nuclear Plant (FNP) Units 1 and 2 approach for complying with Order EA-12-0Sl methods in IIJEI 12-02 with the and as Six month progress reports EA-12-0Sl and in NEI FNP 1 & 2 RSFPI Integrated Plan Page 3 of 16 2/27/2013 PM II. Schedule Installation of reliable spent fuel pool (SFP) level instrumentation will be completed prior to startup from the second refueling outage per unit after submittal of this plan (the Second Refueling outage commencing at FNP following February 28, 2013 is Spring 2015 for Unit 1 and Fall 2014 for Unit 2), but no later than December 31, 2016, (Reference 6). The following milestone schedule is provided.
The dates are planning dates subject to change as design and implementation details are developed.
Any changes to the following target dates will be reflected in the subsequent six (6) month status reports. The current milestones are: Original Target Activity Status Date {Include date changes in this columnl Oct. 2012 Submit 60 Day Status Report Complete Feb . 2013 Submit Overall Integrated Implementation Plan Complete May 2013 Unit 2 1 s RFO Aug 2013 Submit 6 Month Status Report Nov 2013 Unit 1 1 s RFO Dec 2013 Develop Modifications Unit 2 Feb . 2014 Submit 6 Month Status Report Apr 2014 Receipt of Unit 2 SFP Instrument Channel Apr 2014 Develop Modifications Unit 1 June 2014 Receipt of Unit 1 SFP Instrument Channel 3Q2014 Complete Functional Test of Unit 2 SFP Instruments Aug . 2014 Submit 6 Month Status Report 4Q2014 Complete Functional Test of Unit 1 SFP Instruments Nov 2014 Unit 2 Implementation Complete (2 no RFO)* Feb . 2015 Submit 6 Month Status Report Apr 2015 Unit 1 Implementation Complete (2 no RFO)* June 2015 Submit Completion Report
- Full compliance after second listed refueling outage FNP 1 & 2 RSFPI Integrated Plan Page 4 of 16 2/27/2013 12:19 PM III. Identification of Spent Fuel Pool Water Levels Each unit at Joseph M. Farley Nuclear Plant has its own spent fuel pool. The wet spent-fuel storage facility is located in the Auxiliary Building at EI. 155'-00" in separate rooms. The Unit 1 and Unit 2 wet spent fuel pool storage facilities are made of reinforced concrete and each is lined on the inside with X" thick stainless steel plate. The SFPs are designed to provide underwater storage space for spent fuel assemblies and control rods after their removal from containment.
The SFPs shall maintain enough heat removal capacity to accommodate the assemblies from a full core emergency off-load as well as the spenf fuel assemblies previously discharged to the pool (See Attachment 1). Key spent fuel pool water levels: Level adequate to support operation of the normal fuel pool cooling system -Fuel pool level to support spent fuel pump Net Positive Suction Head (NPSH) requirements is 153'-4". (References 15,16, and 18) Level adequate to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck -Elevation 139'-3/8" is approximately 10'-0" above the highest point of the fuel racks (plus or minus 1 foot). (Reference 10 Figure 9.1-2 (sheet 1 of 2) and References 15 & 16) Level where fuel remains covered -Elevation 129'-3/8" is the nominal level of the highest fuel rack. (Reference 10 -Figure 9.1-2 (sheet 1 of 2) and References 15 & 16) IV. Instruments Design of the instruments will be consistent with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02 with the exceptions and clarifications as detailed below. Primary and backup instrument channels will consist of fixed components. The plan is for both channels to utilize Guided Wave Radar, which functions according to the principle of Time Domain Reflectometry (TDR). A generated pulse of electromagnetic energy travels down the probe. Upon reaching the liquid surface the pulse is reflected and based upon reflection times, level is inferred. The measured range will be continuous from the high pool level elevation 153'-10" to the top of the spent fuel racks at elevation 129'-3/8" (Reference 10 -Figure 9.1-2 (sheet 1 of 2) and References 15, 16, 17, & 18). Instrument channel level sensing components (probe) will be located in the SFP directly adjacent to the spent fuel. The electronics processing module will be capable of being located in a non-harsh environment area outside the SFP area. The display shall provide a continuous indication of spent fuel pool water level at the Display location.
In the event the link to the Display is lost, a field accessible signal/Indication (remote to the Display location) will be available for determination of pool level. FNP 1 & 2 RSFPI Integrated Plan Page 5 of 2/27/2013 12:19 PM The electronic processing module and the Display will be installed in a location that will meet the criteria established in NEI12-02 and endorsed by NRC 03 . The specific location of the electronic processi ng modu Ie and the Display has not been determined yet. V. Reliability Reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 or NEI12-02 , as discussed in Section 3.4, Qualification and 3.8 Testing. Reliable level indication will be functional during all times when used fuel is in the SFP cons i stent with NEI 12-02 Section 4.3, Testing and Calibration. VI. Instrument Channel Design Criteria Instrument channel design will meet the guidelines of NRC JLD-ISG-2012-03 and NE112-02 and applicable sections of the plant FSAR with the exceptions and clarifications as detailed below. Arrangement SFP level probes will be installed separate from each other in the SFP. Primary and backup level indication will be installed in the Main Control Room, at the alternate shutdown panel, or another appropriate and accessible location (reference NEI12-06) that complies with the NEI12-02 following characteristics. SNC has not determined the exact location at this time and has several options that provide various benefits . For example, the Main Control Room is the NRC preferred location while an appropriate accessible location in the plant would provide information to personnel in the plant at a location closer to the pool and mitigation equipment.
Both existing and new barr i ers will be used to provide a level of protection for the cable located on the refueling floor from falling debris missiles generated by the event. Probes will consist of a small diameter stainless steel cable mounted within a protective sleeve (stilling well). The ca ble w i ll end just above the fuel racks. Based on the light weight of the probe, it is assumed that the probe will survive the event with little or no damage. Likewise , the pool wall or spent fuel will not be damaged by any interaction with the protective sleeve during the event. Specific channel level sensing components physical propert i es and installation details will be provided later after the engineering and design phase is completed . The probe support (including stilling well) will be designed to shield the probe from event generated missiles (falling debris). The design of the probe and probe support will allow the fuel handling machine to pass over it without interference.
Cabling for power supplies and indications for each channel will be separated for missile protection (falling debris) and routed in separate conduits from cabling for the other channel. FNP 1 & 2 RSFPI Integrated Plan Page 6 of 2/27/2013 12:19 PM BMounting Per NEI 12-02 Section 3.3, Mounting, the new equipment will be mounted to maintain the current Seismic Class of the Spent Fuel Pool which is Seismic Class I (Reference Section 3.8.4). Thus, the new equipment will be seismically qualified to Class I. In addition, the mounting of the primary and backup channel components throughout the plant will meet the criteria of the structure it will be routed through or attached to. (refer to Qualification details below relating to cable and raceway installation criteria)
C. Qualification The components/cables/connections for both primary and backup channels will be reliable at the temperature, humidity, and radiation levels consistent with the spent fuel pool water at saturation conditions for seven (7) days. Saturation temperature at the bottom of the SFP assuming normal water level will be approximately 250°F. Post event temperature at sensors located above the SFP is assumed to be 212°F. Post event humidity in the SFP room is assumed to be 100% with condensing steam. The components/cables/connections will be qualified for expected conditions at the installed location assuming the SFP has been at saturation for an extended period. The components/cables/connections located in the vicinity of the SFP will be qualified to withstand peak and total integrated dose radiation levels for their installed location assuming that post event SFP water level is equal to the top of irradiated fuel for a time no greater than six (6) hours. It is anticipated that the station personnel can align one of the three (3) SFP Cooling Strategies as detailed in NEI 12-06 if conditions are degrading as indicted by decreasing SFP level. Conduit design in the SFP area will be installed to Seismic Category 1 criteria.
Both existing and new barriers will be used to provide a level of protection for the cable located on the refueling floor from missiles.
The existing and new raceway used to route the cable to the Display will be installed to Seismic Class 1 criteria.
Augmented quality requirements, similar to those applied to fire protection, will be applied to the components installed in response to this Order. The specific values to use for the shock and vibration qualification will be determined in the design phase of the implementation using FSAR and Design Basis information.
Components of the instrument channels installed in the SFP area will be qualified for shock and vibration using one or more of the following methods (note different methods may be used for the various sub components of the primary and back-up instrument channels): Instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as IS09001, Quality management systems -Requirements (Reference 8)) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in environments where significant shock and vibration loadings are common, such as for portable hand-held devices or transportation applications; FNP 1 & 2 RSFPI Integrated Plan Page 7 of 2/27/2013 12:19 PM reliability in environments with shock applications; or Use of components inherently resistant to shock and vibration loadings or are reliable as For impact on instrument channel components required after a potential event for installed components, the to verify and is adequate.
components instrument channels are rated by the manufacturer
{or tested} for seismic impact at commensurate with of basis event in the area channel use using one or more of the following methods different methods may used for the various sub components primary back-up instrument channels): Adequacy of seismic and installation is demonstrated based on guidance in Sections 7,8,9, and 10 of IEEE Standard IEEE Recommended Practice 1E Nuclear Power industrial standard Instrument channel use known principles are by manufacturers with commercial quality programs (such as 1509001) with seismic requirements included in the purchase specification and/or instrument and commercial design and for operation in environments where seismic effects are common I reliability in environments with hand-held or transportation applications Demonstration of reliability using methods that predict the equipment's performance by: Analysis of the equipment under simulated Using a combination test and The use Demonstration that devices are substantially similar in design to models been previously for seismic in excess of the nt design at the location the instrument is to installed (g-Ievels a uency qualification using seismic motion consistent with that of design loading at the installation location.
FNP 1 & 2 Integrated Plan Page 8 of 12:19 PM Independence The primary and backup instrument channels are of the same technology, are permanently installed, separated by distance or barriers, and utilize independent power supplies from different buses/switchgear. Power Supplies Each channel will normally be powered from independent (different buses/switchgear) 120V AC power sources and will have a dedicated battery backup. The battery backup will be dedicated to each channel, should have the capability of automatically switching and operating on backup batteries and will have manual switching as a minimum. A minimum battery life of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be provided to allow for power restoration from portable equipment (refer to attachment 2 for a typical sketch). Refer to Safety Function Support section of the SNC Integrated Plan February 28, 2013, submittal for NRC Order EA-12-049 for details on the power strategy from portable FLEX Diesel Generators (DGs). Accuracy Instrument channels will be designed such that they will maintain their design accuracy without recalibration following a power interruption or change in power source. SNC plans for the instrument design accuracy to be within +/- 1 inch, or as close as reasonably achievable, over the entire range for the expected environmental and process conditions. Accuracy will consider SFP post event conditions, e.g., saturated water, steam environment, or concentrated borated water. Additionally, the instrument accuracy of the GWR technology will be sufficient to allow trained personnel to determine when the actual level exceeds the specified level of each indicating range (levels 1, 2 and 3) without conflicting or ambiguous indication.
The accuracy will be within the resolution requirements of Figure 1 of NEI12-02. Testing Instrument channel design will provide for routine testing and calibration consistent with Order EA-12-0S1 and the guidance in NEI 12-02. SNC plans for the design to facilitate in-situ testing and lor calibration of the Static or non-active installed (fixed) sensors SNC plans for the design to facilitate the microprocessor based channel features to be capable of testing while mounted in the pool. Existing work control processes will be used to control maintenance and testing. (e.g., Preventive Maintenance Program, Surveillance Program, Vendor Contracts, or work orders) Other testing and calibration requirements are located in Program Controls testing sub section below. FNP 1 & 2 RSFPI Integrated Plan Page 9 of 2/27/2013 12:19 PM H. Display Primary and backup indication will be provided in the Main Control Room, at the alternate shutdown panel, or another appropriate and accessible location (reference NEI12-06) that complies with the NEI12-02 characteristics.
If multiple display locations are powered from the instrument loop, then the guidance in NE112-02 regarding mUltiple displays will be followed (refer to attachment 2 for a typical sketch). VII. Instrument Channel Program Criteria Instrument channel program criteria will be consistent with the guidelines of NRC 03 and NEI12-02.
A. Training A systematic approach will be used to identify the population to be trained and to determine both the initial and continuing elements of the required training.
Personnel will complete training prior to being assigned responsibilities associated with this instrument.
B. Proced ures Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation, and abnormal response issues associated with the new SFP instrumentation consistent with NEI 12-02. Procedures will address a strategy to ensure SFP water level addition is initiated at an appropriate time consistent with implementation of NEI12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide (References 5 and 7). C. Testing and Calibration Processes will be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup spent fuel pool level instrument channels to maintain the instrument channels at the design accuracy.
Testing and calibration of the instrumentation will be consistent with vendor recommendations and any other documented basis. Calibration will be specific to the mounted instrument and the monitor. Out of service time as identified in NEI 12-02 will be incorporated consistent with the programmatic process used for compliance with NRC Order EA-12-049 (Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events). FNP 1 & 2 RSFPI Integrated Plan Page 10 of 16 2/27/2013 12:19 PM VIII. Need for Relief and Basis Southern Nuclear is not requesting relief from the requirements of Order EA-12-051 or the guidance in NE112-02 at this time, except as discussed herein. Consistent with the requirements of Order EA-12-051 and the guidance in NEI 12-02 as endorsed by NRC JLO-ISG-2012-03, the six-month reports will delineate progress made, any proposed changes in our compliance methods, updates to the schedule, and, if needed, requests for relief and their bases. IX. References EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, March 12, 2012 2) EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements Mitigation Strategies for Beyond-Oesign-Basis External Events, March 12, 3) NRC JLO-ISG-2012-03, Compliance with Order EA-12-051, Reliable Spent Fuel Instrumentation, Revision 0, August 29,2012 4) NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," Revision 1, August 2012 5) NE112-06, Oiverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 0, August 2012 Letter, NL-12-2150, Initial Status Report in Response to Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated October 23,2013 Letter NL-12-2145, Initial Status Report in Response to Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Oesign-Basis External Events (Order Number EA-12-049), dated October 23,2013 8) IS09001, Quality management systems -Requirements
- 9) IEEE Standard 344-2004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations 10) Joseph M. Farley Nuclear Plant Unit 1 and 2 Final Safety Analysis Reports, Revision 25, Nov. 2012 11) 0-175043, "P&IO -Spent Fuel Pool Cooling System" -Unit 1 12) 0-205043, "P&IO -Spent Fuel Pool Cooling System" -Unit 2 13) 0-350804, Ver. 17.0, "Aux. Bldg Cone. Penetration Seals @ EI 155' -0" (PS-155-00)" 14) 0-356039, Ver. 11.0, "Aux. Bldg Concrete Penetration Seals Key Plan @ EI155' _0" (2PS-155-00)" 15) 0-176542, Ver. 15.0, "Section 20 Concrete Auxiliary Building" 16) 0-206542, Ver. 6.0, "Sect 20 Cone AlB" 17) U-266647, Ver. 14.0, "Precautions, Limitations and Setpoints for Nuclear Steam Supply Systems" 18) A-181014, Ver. 14.0, "Functional System Oescription Spent Fuel Pool System" FNP 1 & 2 RSFPI Integrated Plan Page 11 of 2/27/2013 12:19 PM Attachment 1: Probe Location Sketch" (Page 1 of 2)
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