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| | {{#Wiki_filter:Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc. May 21 , 201 4 Docket Nos.: 50-348 50-364 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 sou NL-14-0805 Joseph M. Farley Nuclear Plant-Units 1 and 2 Additional Information Regarding the Request for Extension of Flood Hazard Reevaluation Report Due Date |
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| | ==References:== |
| | : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident; dated March 12, 2012. (ML 12053A340) 2. Letter to NRC, Southern Nuclear Operating Company Request to Obtain U.S. Army Corps of Engineers (USAEC) Information, dated September 26, 2013. (ML13274A343) 3. Letter to NRC, Joseph M. Farley Nuclear Plant-Units 1 and 2 Request for Extension of Flood Hazard Reevaluation Report Due Date, dated February 28, 2014. (ML 14072A486) Ladies and Gentlemen: On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee perform and submit a Flood Hazard Reevaluation Report (FHRR). In order to fully perform this reevaluation for the Joseph M. Farley Nuclear Plant (FNP) site, Southern Nuclear Operating Company (SNC) submitted Reference 2 requesting specific information be obtained by the NRC from the U.S. Army Corps of Engineers (USAGE) and be provided to SNC. To meet all of the requirements of Reference 1, SNC submitted Reference 3 which outlined the need for an extension request to provide the FHRR 120 days after the USAGE flooding analysis information is received. |
| | U.S. Nuclear Regulatory Commission NL-14-0805 Page2 On May 16, 2014 during a public teleconference with members of the NRC staff, SNC agreed to provide additional information which the NRC has requested in order to grant the extension. Portions of the FHRR have already been completed which SNC has determined to result in a higher than anticipated Local Intense Precipitation ponding level at FNP. The highest potential ponding level during the LIP event at the doors leading to safety related equipment is, in most cases, less than 6 inches. This level follows a rainfall event that includes 19.33 inches in one hour. The hydrodynamic effects associated with the ponding are minimal. As a result, an attachment to FNP-0-AOP-21 has been drafted which includes detailed instruction regarding the use of sandbags near specific doors to keep water from entering the buildings. As a normal practice, the National Weather Service is monitored and if an event of the above-stated magnitude is a potential, the draft AOP-21 attachment would be used by FNP. Sand and sandbags have been ordered and will be available to implement this draft procedure by June 1, 2014. These interim actions will be discussed further when the FHRR is submitted. This letter contains no new regulatory commitments. If you have any questions, please contact John Giddens at 205.992.7924. Respectfully submitted, C.R. Pierce Regulatory Affairs Director CRP/JMG cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President -Farley Mr. B. L. lvey, Vice President-Regulatory Affairs Mr. B. J. Adams, Vice President-Engineering Mr. D. R. Madison, Vice President-Fleet Operations RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley Alabama Department of Public Health Dr.D. E. Williamson, State Health Officer}} |
Revision as of 10:08, 28 June 2018
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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] |
Text
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc. May 21 , 201 4 Docket Nos.: 50-348 50-364 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Tel 205.992.7872 Fax 205.992.7601 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 sou NL-14-0805 Joseph M. Farley Nuclear Plant-Units 1 and 2 Additional Information Regarding the Request for Extension of Flood Hazard Reevaluation Report Due Date
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident; dated March 12, 2012. (ML 12053A340) 2. Letter to NRC, Southern Nuclear Operating Company Request to Obtain U.S. Army Corps of Engineers (USAEC) Information, dated September 26, 2013. (ML13274A343) 3. Letter to NRC, Joseph M. Farley Nuclear Plant-Units 1 and 2 Request for Extension of Flood Hazard Reevaluation Report Due Date, dated February 28, 2014. (ML 14072A486) Ladies and Gentlemen: On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee perform and submit a Flood Hazard Reevaluation Report (FHRR). In order to fully perform this reevaluation for the Joseph M. Farley Nuclear Plant (FNP) site, Southern Nuclear Operating Company (SNC) submitted Reference 2 requesting specific information be obtained by the NRC from the U.S. Army Corps of Engineers (USAGE) and be provided to SNC. To meet all of the requirements of Reference 1, SNC submitted Reference 3 which outlined the need for an extension request to provide the FHRR 120 days after the USAGE flooding analysis information is received.
U.S. Nuclear Regulatory Commission NL-14-0805 Page2 On May 16, 2014 during a public teleconference with members of the NRC staff, SNC agreed to provide additional information which the NRC has requested in order to grant the extension. Portions of the FHRR have already been completed which SNC has determined to result in a higher than anticipated Local Intense Precipitation ponding level at FNP. The highest potential ponding level during the LIP event at the doors leading to safety related equipment is, in most cases, less than 6 inches. This level follows a rainfall event that includes 19.33 inches in one hour. The hydrodynamic effects associated with the ponding are minimal. As a result, an attachment to FNP-0-AOP-21 has been drafted which includes detailed instruction regarding the use of sandbags near specific doors to keep water from entering the buildings. As a normal practice, the National Weather Service is monitored and if an event of the above-stated magnitude is a potential, the draft AOP-21 attachment would be used by FNP. Sand and sandbags have been ordered and will be available to implement this draft procedure by June 1, 2014. These interim actions will be discussed further when the FHRR is submitted. This letter contains no new regulatory commitments. If you have any questions, please contact John Giddens at 205.992.7924. Respectfully submitted, C.R. Pierce Regulatory Affairs Director CRP/JMG cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President -Farley Mr. B. L. lvey, Vice President-Regulatory Affairs Mr. B. J. Adams, Vice President-Engineering Mr. D. R. Madison, Vice President-Fleet Operations RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley Alabama Department of Public Health Dr.D. E. Williamson, State Health Officer