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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) 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 ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public 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 ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals 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 ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report 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 IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) 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-23-0713, 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-23-0704, 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 IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 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 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) 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 ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter 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 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 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 2024-01-30
[Table view] Category:Report
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 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 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 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 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 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 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 ML14051A7342014-02-20020 February 2014 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 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 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 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 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 2022-07-14
[Table view] Category:Miscellaneous
MONTHYEARML21214A3182021-08-0202 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. 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 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 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 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 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 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 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 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 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 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 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 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 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 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, 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 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 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 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 ML13004A2572012-11-26026 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 232 of 467 Through Attachment 3, Page 306 of 467 ML13004A2562012-11-26026 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 177 of 467 Through Attachment 3, Page 231 of 467 ML13004A2552012-11-26026 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 123 of 467 Through Attachment 3, Page 176 of 467 ML13004A2542012-11-26026 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 58 of 467 Through Attachment 3, Page 122 of 467 ML13004A2532012-11-26026 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 1, Page 1 of 26 Through Attachment 3, Page 57 of 467 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 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 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 2021-08-02
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Charles R. Pierce Regulatory Affairs Director Juyte 3, 2014 Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway P.O. Box 1295 I BIN 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2-STAFF ASSESSMENT OF THE FLOODING WALKDOWN REPQRT SUPPORTING IMPLEMENTATION.OF NEAR-TERM TASK FORCE RECOMMENDATION
2.3 RELATED
TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT (TAG NOS. MF0226 AND MF0227)
Dear Mr. Pierce:
On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information letter per Title 10 of the Code of Federal Regulations, Subpart 50.54(f) (50.54(f) letter). The 50.54(f) letter was issued to power reactor licensees and holders of construction permits requesting addressees to provide further information to support the NRC staff's evaluation of regulatory actions to be taken in response to lessons learned from Japan's March 11, 2011, Great Tohoku Earthquake and subsequent tsunami. The request addressed the methods and procedures for nuclear power plant licensees to conduct flooding hazard walkdowns to identify and address degraded, nonconforming, or unanalyzed conditions through the corrective action program, and to verify the adequacy of the monitoring and maintenance procedures.
By letter datec:l November 27, 2012, Southern Nuclear Operating Company, Inc., submitted a Flooding Wafkdown Report as requested in Enclosure 4 of the 50.54(f) letter for the Joseph M. Farley Nuclear Plant, Units 1 and 2. By letter dated January 29, 2014, Southern Nuclear Operating Company, Inc., provided a response to an NRC request for additional information.
The NRC staffreviewed the information provided and, as documented in the enclosed staff assessment, determined sufficient information was provided to be responsive to Enclosure 4 of the 50.54(f) letter.
C. Pierce* If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@
nrc.gov. Docket No. 50-348 and 50-364
Enclosure:
Staff Assessment of Flooding Walkdown Report cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation "
STAFF ASSESSMENT OF FLOODING WALKDOWN REPORT NEAR-TERM TASK FORCE RECOMMENDATION
2.3 RELATED
TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT SOUTHERN NUCLEAR OPERATING COMPANY, INC. JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 INTRODUCTION On March 12, 2012, 1 the U.S. Nuclear Regulatory Commission (NRC) issued a request for information per Title 10 of the Code of Federal Regulations, Subpart 50.54(f) (50.54(f) letter) to all power reactor licensees and holders of construction permits in active or deferred status. The request was part of the implementation of lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 4, "Recommendation 2.3: Flooding," 2 to the 50.54(f) letter requested licensees to conduct flooding walkdowns to identify and address degraded, nonconforming, or unanalyzed conditions using the corrective action program (CAP), verify the adequacy of monitoring and maintenance procedures, and report the results to the NRC. Enclosure 4 of the 50.54(f) letter requested licensees to include the following:
- a. Describe the design basis flood hazard level(s) for all flood-causing mechanisms, including groundwater ingress. b. Describe protection and migration features that are considered in the licensing basis evaluation to protect against external ingress of water into structures, systems, and components (SSCs) important to safety. c. Describe any warning systems to detect the presence of water in rooms important to safety. d. Discuss the effectiveness of flood protection systems and exterior, incorporated, and temporary flood barriers.
Discuss how these systems and barriers were evaluated using the acceptance criteria developed as part of Requested Information item 1.h. e. Present information related to the implementation of the walkdown process (e.g., details of selection of the walkdown team and procedures) usingthe documentation template discussed in Requested Information item 1.j, including actions taken in response to the peer review. f. Results of the walkdown including key findings and identified degraded, nonconforming, or unanalyzed conditions.
Include a detailed description of the actions *taken or planned to address these conditions using guidance in Regulatory Issues Summary 2005-20, Revision 1, Revision to the .NRC Inspection Manual Part 9900 Technical Guidance, 1 ADAMS Accession No. ML 12053A340.
2 ADAMS Accession No. ML 12056A050.
2 -"Operability Conditions Adverse to Quality or Safety," including entering the condition in the corrective action program. g. Document any cliff-edge effects identified and the associated basis. Indicate those that were entered into the* corrective action program. Also include a detailed description of the actions taken or planned to address these effects. h. Describe any other planned or newly installed flood protection systems or flood mitigation measures including flood barriers that further enhance the flood protection.
Identify results and any subsequent actions taken in response tO the peer review. In accordance with the 50.54(f) letter, Enclosure 4, Required Response Item 2, licensees were required to submit a response within 180 days of the NRC's endorsement of the flooding walkdown guidance.
By letter dated May 21, 2012 3 , the Nuclear Energy Institute (NEI) staff submitted NEI 12-07, Revision 0 A, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features" to the NRC staff to consider for endorsement.
By letter dated May 31, 2012 4 , the NRC staff endorsed the walkdown guidance.
By letter dated November 27, 2012 5 , Southern Nuclear Operating Company, Inc. (Southern Company, the licensee), provided a response to Enclosure 4 of the 50.54(f) letter Required Response Item 2, for the Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP). The NRC staff issued a request for additional information (RAI) to the licensee regarding the available physical margin (APM) dated December 23, 2013 6. The licensee responded by letter dated January 29, 2014 7. The NRC staff evaluated the licensee's submittals to determine if the information provided in the walkdown report met the intent of the walkdown guidance and if the licensee responded appropriately to Enclosure 4 of the 50.54(f) letter. 2 REGULATORY EVALUATION The SSCs important to safety in operating nuclear power plants are designed either in accordance with, or meet the intent of Appendix A to 10 CFR Part 50, General Design Criteria (GDC) 2: "Design Bases for Protection Against Natural Phenomena;" and Appendix A to 10 CFR Part 100, "Reactor Site Criteria." GDC 2 states that SSCs important to safety at nuclear power plants shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.
For initial licensing, each licensee was required to develop and maintain design bases that, as defined by 10 CFR 50.2, identify the specific functions that an SSC of a facility must perform, and the specific values or ranges of values chosen for controlling parameters as reference bounds for the design. 3 ADAMS Package Accession No. ML 121440522.
4 ADAMS Accession No. ML 12144A142.
5 ADAMS Accession No. ML 12333A 146. 6 ADAMS Accession No. ML 13325A891 . 7 ADAMS Accession No. ML14031A209. The design bases for the SSCs reflect appropriate consideration of the most severe natural phenomena that have been historically reported for the site and surrounding area. The design
- bases also reflect sufficient margin to account for the limited accuracy, quantity, and period of time in which the historical data have been accumulated.
The current licensing basis (CLB) is the set of NRC requirements applicable to a specific plant, including the licensee's docketed commitments for ensuring compliance with, and operation within, applicable NRC requirements and the plant-specific design basis, including all modifications and additions to such commitments over the life of the facility operating license. 3 TECHNICAL EVALUATION
3.1 Design
Basis Flooding Hazard For Joseph M. Farley Nuclear Plant, Units 1 & 2 The design basis flood hazard for the site is a Probable Maximum Flood (PMF) in combination with upstream Chattahoochee River dam failures and a 40 mile per hour (mph) wind as the current licensing basis (CLB) flood. The maximum flood elevation from these combined events including wind induced wave run-up is 153.7 ft. mean see level (MSL). The finished plant grade *is at elevation 154.5 ft. MSL. Based on the flood hydrograph for the probable maximum precipitation (PMP) storm event as developed in the FNP UFSAR, the resulting peak Chattahoochee River discharge and stage is estimated to occur approximately 17 days after the initiation of the PMP*storm event. The licensee stated that FNP is considered a dry site as per definition provided in NRC Regulatory Guide 1.59. The licensee also described probable maximum precipitation impacts to the site, on-site storage pond failure, and groundwater conditions.
However, the PMF on the Chattahoochee River as described above is the CLB flood event. Flooding from ice-dams was considered highly unlikely as there is no historical record of the Chattahoochee River freezing.
The design groundwater level for the plant is 140.0 ft MSL. Based on its review, the NRC staff concludes that the licensee has described the design basis flood hazard level(s) as indicated in Requested Information item 2.a of the 50.54(f) letter, consistent with Appendix D, Walkdown Report, of the walkdown guidance.
3.2 Flood
Protection and Mitigation
3.2.1 Flood
Protection and Mitigation Description The licensee stated that there are no safety-related systems or components located below the CLB flood level with the powerblock finished grade and floor elevations at 154.5 and 155.0 ft MSL, respectively.
The current licensing basis flood protection features at FNP are passive. The licensee stated that passive features are credited for mitigating floods from surface and subsurface sources and are independent of operating mode and include topography and exterior walls (including penetrations, seals and waterstops).
The licensee stated that none of safety-related facilities are susceptible to flooding as the powerblock area is at 154.5 ft. MSL while the PMF is at 153.7 ft. MSL. In addition, the licensee stated that the powerblock area is protected from failure of the ultimate heat sink (UHS) cooling water storage pond, as the water released is diverted away from the power block by the dam and dike, as well as the topography between the pond and the power block.
- 3.2.2 Incorporated and Exterior Barriers.
The site has incorporated and/or exterior barriers that are permanently in-place, requiring no operator manual actions. The licensee stated that the topography at the site is such that no safety-related facilities are exposed to flooding as the final plant grade is above the flood elevation level and wall penetrations below elevation 154.5 ft. MSL are sealed. In addition, any possible flooding from the failure of the UHS cooling water storage pond is mitigatedby natural drainage features and the topography between the powerblock and the storage pond. 3.2.3 Temporary Barriers and Other Manual Actions The licensee stated that FNP does not rely upon active or temporary features for protection.
3.2.4 Reasonable
Simulations and Results The licensee did not discuss reasonable simulations in the flood walkdown report. No operator actions or instrumentation are credited to protect the FNP from external floods for Units 1 and 2. 3.2.5 Conclusion Based on the NRC staff's review, the staff concludes that the licensee has described protection and mitigation features as indicated in Requested InformatiOn item 2.b of the 50.54(f) letter consistent with Appendix D, Walkdown Report, of the walkdown guidance.
3.3 Warning
Systems The licensee stated that there are installed warning systems at the FNP site for internal plant flooding conditions, such as control room annunciation of high water level in drain sumps, but they are outside the scope of the NTTF 2.3 recommendations since they are not intended for external flooding events. The licensee refers to the FNP FSAR Chapter 9 for several design features that provide sufficient warning time for an operator to identify and isolate a postulated flood prior to affecting safety-related equipment; however, no details on these features or warning times are provided.
Preparation in advance of these adverse weather conditions is governed by corporate programs and procedures, including abnormal operating procedure FNP-0-AOP-21.0 "S.evere Weather.
Based on the NRC staff's review, the staff concludes that the licensee has provided information to describe any warning systems as indicated in Requested Information item 2.c of the 50.54(f) letter, consistent with Appendix D, Walkdown Report, of the walkdown guidance.
3.4 Effectiveness
of Flood Protection Features The licensee stated that flood protection features are considered acceptable if they are within FNP's current licensing basis (CLB) and have no identified adverse quality conditions.
The licensee reaffirmed that none of the safety-related facilities are susceptible to surface flooding as the powerblock is at a higher elevation than the PMF. In addition, the licensee confirmed that no operator actions, temporary barriers or non-CLB structures are credited for protection against flooding in the FNP CLB. Additionally, the licensee stated that corporate programs and procedures govern FNP's preparation against adverse weather conditions.
- Regarding incorporated barriers, the licensee stated that all barriers at FNP are passive and include: walls and sealed penetrations, topography and yard drainage systems. The licensee discussed that during the flooding walkdowns, these features were inspected and assessed.
Based on the NRC staff's review, the staff concludes that the licensee has discussed the effectiveness of flood protection features as indicated in Requested Information item 2.d of the 50.54(f) letter consistent with Appendix D, Walkdown Report, of the walkdown guidance.
3.5 Walkdown
Methodology The licensee's walkdown submittal dated November 27, 2012, indicated that the licensee implemented the walkdowns in accordance with the NRC endorsed guidance provided in NEI 12-07, "Guideliqes for Performing Verification Walkdowns of Plant Flood Protection Features." 8 The licensee's walkdown submittal dated November 27, 2012, indicated that the licensee implemented the walkdowns consistent with the intent of the guidance provided in NEI 12-07. The licensee did not identify any exceptions from NEI 12-07. Based on its review, the NRC staff concludes that the licensee has presented information related to the implementation of the walkdown process as indicated in Requested Information item 2.e of the 50.54(f) letter, consistent with Appendix D, Walkdown Report, of the walkdown guidance.
3.6 Walkdown
Results 3.6.1 Walkdown Scope The licensee performed walkdowns of 86 flood protection areas for features that include site topography, exterior walls (including penetration seals and waterstops), piping and electrical tunnels, and the UHS storage pond dike. The licensee noted that the site topography has not been altered significantly from the CLB. Condition reports were issued for 32 degraded conditions, including deteriorated door seals and thresholds, minor cracks in concrete walls, piping and electrical seals, and stains on walls. The licensee used acceptance criteria consistent with the intent of NEI 12-07. 3.6.2 Licensee evaluation of flood protection effectiveness.
key findings, and identified deficiencies The licensee performed an evaluation of the overall effectiveness of the plant's flood protection features.
The licensee, as described previously, stated that flood prevention features at FNP are passive. The walkdowns focused on the adequacy of features such as site topography, walls, penetration seals, doors, and piping and electrical tunnels. NEI 12-07 defines a deficiency as follows: "a deficiency exists when a flood protection feature is unable to perform its intended function when subject to a design basis flooding hazard." The licensee identified one deficiency during the course of the flood walkdowns.
The deficiency was related to a partially blocked Service Water Culvert which was dispositioned and resolved through FNP's CAP system. 8 ADAMS Accession No. ML 12173A215. NEI 12-07 specifies that licensees identify observations/potential deficiencies in the CAP that were not yet dispositioned at the time the walkdown report was submitted.
FNP identified a total of 32 degraded conditions during the flooding walkdowns that were entered into the plant's CAP. These conditions include: exterior door seals and thresholds, minor cracks in concrete walls, piping and electrical seals, and stains on walls. The licensee determined that these features were capable of performing their intended flood protection functions and therefore were not reported to the NRC. 3.6.3 Flood Protection and Mitigation Enhancements The licensee determined that no additional enhancements that improve or increase flood protection or mitigation are necessary.
3.6.4 Planned
or newly installed features The licensee did not determine that changes were necessary by the flooding walkdowns.
3.6.5 Deficiencies
Noted and Actions Taken or Planned to Address The licensee noted one deficiency related to debris blockage at the Service Water Culvert. This deficiency was dispositioned and resolved through FNP's CAP system. The culvert was blocked with soil and debris, thereby decreasing its discharge capacity which could impact the plant during a PMP event. 3.6.6 Staff Analysis of Walkdowns The NRC staff reviewed the licensee walkdown report dated November 27, 2012. The NRC staff noted that the licensee followed the recommended walkdown guidance without exception.
Degraded conditions for flood protection and available physical margin (APM) features were entered into the plant's CAP for dispositioning.
The licensee identified one deficiency which was promptly resolved.
The licensee stated that all other degraded flood protection features were determined to be capable of performing their intended flood protection function.
The licensee did not discuss reasonable simulations and noted that preparation for adverse weather conditions is governed by corporate programs and procedures including procedure FNP-0-AOP-21.0 "Severe Weather".
Based on its review, the NRC staff concludes that the licensee has provided results of the walkdown and described any other planned or newly installed flood protection systems or flood mitigation measures as indicated in Requested Information items 2.f and 2.h of the 50.54(f) letter consistent with Appendix D, Walkdown Report, of the walkdown guidance.
Based on the information provided in the licensee's submittals, the NRC staff concludes that the licensee's implementation of the walkdown process meets the intent of the walkdown guidance.
3.6.7 Available
Physical' Margin The NRC staff submitted a request for additional information (RAI) to the licensee regarding the available physical margin (APM) dated December 23, 2013 9. The licensee responded with the 9 ADAMS Accession No. ML 13325A891. letter dated January 29, 2014. The licensee has reviewed their APM determination process, and entered any unknown APMs into their CAP. The NRC staff reviewed the response, and concluded that the licensee met the intent of the APM determination per NEI 12-07. Based on its review, the NRC staff concludes that the licensee has documented the information requested for any cliff-edge effects, as indicated in Requested Information item 2.g of the 50.54(f) letter consistent with Appendix D, Walkdown Report, of the walkdown guidance.
Further, the NRC staff reviewed the response, and concludes that the licensee met the intent of the APM determination per NEI 12-07. 3.7 NRC Oversight
3.7.1 Independent
Verification by Resident Inspectors . On June 27, 2012, the NRC issued Temporary Instruction (TI) 2515/187 "Inspection of Near-Term Task Force Recommendation
2.3 Flooding
Wal.kdowns." In accordance with the Tl, NRC inspectors independently verified that the licensee implemented the flooding walkdowns consistent with the intent of the walkdown guidance.
Additionally, the inspectors independently performed walkdowns of a sample of flood protection features.
The integrated inspection report dated May 2, 2013 10 , documents the results of this inspection.
No findings of significance were identified.
4 SSCS NOT WALKED DOWN The licensee identified inaccessible features but no restricted access features.
4.1 Restricted
Access The licensee did not identify any restricted access features.
4.2 Inaccessible
Features The licensee stated that eight (8) areas were innaccesible to the walkdown teams. The licensee provided a basis for reasonable assurance that inaccessible access features are available and will perform credited functions.
The inaccessible areas include walls in high radiation areas, walls in elevator shafts, and walls in the spent fuel pool. The licensee provided justification for walls in high radiation areas and elevator shafts being able to perform their intended as the condition of similar features in adjacent and accessible areas. Justification for the condition of walls in the spent fuel pool area included lack of penetrations or credible leakage pathways, thick walls, waterproofing membranes, and continual monitoring of the pool. The licensee noted that a work order was written to investigate and repair a possible in-leakage of ground water through the seismic joint between the Auxiliary and Containment building.
10 ADAMS Accession No. ML 13123A 182. 5 CONCLUSION The NRC staff concludes that the licensee's implementation of flooding walkdown methodology meets the intent of the walkdown guidance.
The NRC staff concludes that the licensee, through the implementation of the walkdown guidance activities and, in accordance with plant processes and procedures, verified the plant configuration with the current flooding licensing basis; addressed degraded, nonconforming, or unanalyzed flooding conditions; and verified the adequacy of monitoring and maintenance programs for protective features.
Furthermore, the licensee's walkdown results, which w_ere verified by the NRC staff's inspection, identified no immediate safety concerns.
The NRC staff reviewed the information provided and determined that suffiCient information was provided to be responsive to Enclosure 4 of the 50.54(f) letter.
C. Pierce If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@
nrc.gov. Sincerely, /RAJ Shawn Williams, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-348 and 50-364
Enclosure:
Staff Assessment of Flooding Walkdown Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsNroDsea Resource RidsNrrDorl Resource RKuntz, NRR CCook, NRO MJardaneh, NRO RidsRgn2MaiiCenter Resource RidsOpaMail Resource RidsNrrLASFigueroa Resource RidsNrrPMFarley Resource Akock, NRO RKaras, NRO EMiller, NRR ADAMS A ccess1on N b ML 14128A08 urn er: 3 OFFICE DORULPL2-1/PM DORULPL2-1
/LA NAME SWilliams SFigueroa DATE 05/12/14 05/19/14 OFFICE DSEA/RGS2 DORULPL2-1
/BC NAME RKaras
- A Pascarelli DATE 05/07/14 06/03/14 Official Record Copy PChaput, NRO BRini, EDO AI, All, Hill, RIV RidsAcrsAcnw MaiiCTR Resource RidsNrrDorllpl2-1 Resource SFianders, NRO b concurrence
>y e-ma1 JLD/PMB/PM A Kuntz 05/22/14 DORULPL2-1
/PM SWilliams 06/03/14