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| ==References:== | | ==References:== |
| : 1. NRC Letter , "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3 , and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012. 2. JLD-ISG-2013-01, "Guidance For Assessment of Flooding Hazards Due to Dam Failure ," Interim Staff Guidance, Revision 0 , July 29 , 2013 (ML13151A153) | | : 1. NRC Letter , "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3 , and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012. 2. JLD-ISG-2013-01, "Guidance For Assessment of Flooding Hazards Due to Dam Failure ," Interim Staff Guidance, Revision 0 , July 29 , 2013 (ML13151A153) |
| : 3. Letter to NRC , " Joseph M. Farley Nuclear Plant-Units 1 and 2 Request to Obtain U. S. Army Corps of Engineers (USACE) Information Required to Provide Response to March 12, 2012 Request for Information , Recommendation 2.1 ," dated September 26, 2013. Ladies and Gentlemen: | | : 3. Letter to NRC , " Joseph M. Farley Nuclear Plant-Units 1 and 2 Request to Obtain U. S. Army Corps of Engineers (USACE) Information Required to Provide Response to March 12, 2012 Request for Information , Recommendation 2.1 ," dated September 26, 2013. 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 a Flood Hazard Reevaluation (FHR). To adequately provide that report in accordance with the guidance provided in Reference 2, Southern Nuclear Operating Company (SNC) requested that the NRC obtain specific information from the U.S. Army Corps of Engineers (USACE) and for that information to be provided to SNC. On April 29, 2014 at the request of the NRC , representatives of SNC attended a meeting with members of the NRC staff and members of the USACE. As a result of that meeting, SNC desires the NRC also request of the USACE additional specific information regarding flow characterist i cs for the critical flow scenario(s) at the closest HEC-RAS cross section to river miles 46 , 43.8 and 42. This assumes the Joseph M. Farley Nuclear Plant site is at river mile 43.8: | | 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 a Flood Hazard Reevaluation (FHR). To adequately provide that report in accordance with the guidance provided in Reference 2, Southern Nuclear Operating Company (SNC) requested that the NRC obtain specific information from the U.S. Army Corps of Engineers (USACE) and for that information to be provided to SNC. On April 29, 2014 at the request of the NRC , representatives of SNC attended a meeting with members of the NRC staff and members of the USACE. As a result of that meeting, SNC desires the NRC also request of the USACE additional specific information regarding flow characterist i cs for the critical flow scenario(s) at the closest HEC-RAS cross section to river miles 46 , 43.8 and 42. This assumes the Joseph M. Farley Nuclear Plant site is at river mile 43.8: |
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Category:Letter type:NL
MONTHYEARNL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-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 - 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NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers 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. 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Charles R. Pierce Regulatory Affairs Director May 6, 2014 Docket Nos.: 50-348 50-364 Southern Nuclear Operating Company, Inc. 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 Joseph M. Farley Nuclear Plant-Units 1 and 2 NL-14-0732 Request for Additional Information from the U.S. Army Corps of Engineers To S upport Flood Hazard Reevaluation, Reco m mendation 2.1
References:
- 1. NRC Letter , "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3 , and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012. 2. JLD-ISG-2013-01, "Guidance For Assessment of Flooding Hazards Due to Dam Failure ," Interim Staff Guidance, Revision 0 , July 29 , 2013 (ML13151A153)
- 3. Letter to NRC , " Joseph M. Farley Nuclear Plant-Units 1 and 2 Request to Obtain U. S. Army Corps of Engineers (USACE) Information Required to Provide Response to March 12, 2012 Request for Information , Recommendation 2.1 ," dated September 26, 2013. 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 a Flood Hazard Reevaluation (FHR). To adequately provide that report in accordance with the guidance provided in Reference 2, Southern Nuclear Operating Company (SNC) requested that the NRC obtain specific information from the U.S. Army Corps of Engineers (USACE) and for that information to be provided to SNC. On April 29, 2014 at the request of the NRC , representatives of SNC attended a meeting with members of the NRC staff and members of the USACE. As a result of that meeting, SNC desires the NRC also request of the USACE additional specific information regarding flow characterist i cs for the critical flow scenario(s) at the closest HEC-RAS cross section to river miles 46 , 43.8 and 42. This assumes the Joseph M. Farley Nuclear Plant site is at river mile 43.8:
U.S. Nuclear Regulatory Commission NL-14-0732 Page2
- Flow hydrographs for the complete model run.
- Velocity hydrographs for the complete model run.
- Spatial coordinates and projection for each cross section.
- All cross section station and elevation points.
- Left and right bank stations.
- Manning's "n" values or roughness coefficients for the left overbank, channel and right overbank at each cross section. It is requested that results of the information requested above be provided to SNC along with the information that the NRC is already planning to provide. This letter contains no NRC regulatory commitments.
If you have any questions, please contact John Giddens at 205.992.7924.
Respectfully submitted, e.tt t1P C.R. Pierce Regulatory Affairs Director CRP/JMG/RCW cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President
& CEO Mr. D. G. Bast, 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-Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer