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Revision as of 09:17, 30 March 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
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Mr. C. R. Pierce Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 2014 Southern Nuclear Operating Company, Inc. P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2-RELAXATION OF RESPONSE DUE DATES REGARDING FLOODING HAZARD REEVALUATIONS FOR RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF THE INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT (TAC NOS. MF3638 and MF3639) Dear Mr. Pierce: By letter dated March 12, 2012,1 the Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (henceforth referred to as the 50.54(f) letter). The request was issued as a part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to perform a reevaluation of all external flooding hazards using present-day guidance and methodologies. By letter dated May 11, 2012,2 the NRC issued a prioritization of due dates for all sites. The flooding hazard reevaluation report (FHRR) was due on March 12, 2014, for Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley). By letter dated September 26, 2013,3 Southern Nuclear Operating Company, Inc. (Southern, the licensee) requested NRC assistance in obtaining the U.S. Army Corps of Engineers (USACE) analysis of dams that could impact the flood levels at the Farley site. By letter dated February 28, 2014,4 Southern requested a delay in submittal of the FHRR for Farley to within 120 days of receiving the USACE final analysis. The reason for this request is that the USACE analysis is necessary to complete the flooding hazard reevaluation (FHR) and 120 days is necessary to incorporate the results. On May 16, 2014,5 the NRC staff held a public meeting with Southern to discuss the requested extension. On May 21, 2014,6 Southern provided additional information supporting its requested extension for providing the Farley FHRR. 1 The 50.54(f) letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 12053A340. 2 The prioritization letter is available in ADAMS under Accession No. ML 12097 A509. 3 The request for assistance in obtaining USAGE analysis is available in ADAMS under Accession No. ML 13274A343. 4 The extension request from Southern is available in ADAMS under Accession No. ML 14072A486. 5 A summary of the May 16, 2014 meeting is available in ADAMS under Accession No. ML 14134A031. 6 The May 21, 2014 letter is available in ADAMS under Accession No. ML 14141 A629.
C. Pierce -2-The NRC reviewed the justification provided and considered the following factors when reviewing the new schedule:
- Southern has completed the analysis required for the Farley FHR not related to the information request to USAGE and has implemented interim actions to account for the higher than anticipated local intense precipitation event.
- As stated in the NRC's interim staff guidance (ISG) JLD-ISG-2013-01 ,7 "Guidance for Assessment of Flooding Hazards Due to Dam Failure," evaluating flooding hazards for nuclear power plants needs to include consideration of floods resulting from dam failures. The FHR for Farley needs to consider dams that are operated by various government agencies including the USAGE. The NRC has entered into an interagency agreement with the USAGE to provide the necessary information for Farley to complete its FHR. Therefore, the FHRR for Farley cannot be completed until the NRC provides the analysis of the USAGE dams to the licensee.
- As stated in NRC letter dated March 1, 2013,8 "incomplete hazard reports that only contain an analysis of some flooding hazard mechanisms would not be of substantitive benefit for staff and would not be acceptable." Therefore, the information requested from the USAGE is necessary before an FHRR can be acceptably submitted to the NRC in compliance with the request in the 50.54(f) letter.
- The limited duration of the proposed extension (120 days after receiving the necessary information) and the fact that Farley has implemented interim actions to account for unbounded reevaluated flooding hazards support the proposed schedule. Given these considerations, the NRC considers the revised schedule proposed by Southern to be acceptable. Accordingly, and based upon the authority granted to the Director, Office of Nuclear Reactor Regulation, the revised required response date for submitting the FHRR for Farley is 120 days after Southern receives the information from USAGE. The NRC will include the date when the Farley FHRR is due when the requested USAGE information is transmitted to the licensee. The transmittal letter will also note that if the USAGE analysis results in a higher flood hazard relative to the design basis, the NRC staff will request that, within 60 days of receipt of the USAGE analysis, Southern provide interim actions it will take or plans to take to address the higher flooding hazard. 7 JLD-ISG-2013-01 is available in ADAMS under Accession no. ML 13151A153 8 NRC's March 1, 2013 letter is available in ADAMS under Accession no. ML 13044A561.
C. Pierce -3-If you have any questions regarding this matter, or if it is necessary to revise the submittal schedule, please contact your NRC project manager, Shawn Williams, at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov. Docket Nos. 50-348 and 50-364 cc: Listserv Sincerely, Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation C. Pierce -3-If you have any questions regarding this matter, or if it is necessary to revise the submittal schedule, please contact your NRC project manager, Shawn Williams, at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov. Docket Nos. 50-348 and 50-364 cc: Listserv DISTRIBUTION: PUBLIC JLD RIF RidsAcrsAcnw_MaiiCTR Resource RidsNrrOd Resource RidsNrrDorl Resource ADAMS Accession No. ML 1417 4A938 Sincerely, IRA/ Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation RidsNrrDoriLpl2-1 Resource RidsNrrPMFarley Resource RidsNrrLASLent Resource RidsRgn1MaiiCenter Resource *via email MMitchell, NRR DSkeen, JLD EMiller, DORL RTaylor, DSS RKuntz, JLD **Previously concurred OFFICE NRRIJLD/JHMB/PM NRRIJLD/JHMB/LA** N RR!DORULPL2-1/PM* NRRIJLD/JHMB/BC DSENRHM1/BC* NAME JSebrosky Slent SWilliams MMitchel CCook (KErwin for) DATE 07/17/14 06/23/14 07/08/14 07/02/14 06/30/14 OFFICE DSENRHM2/BC* OGC NLO NRRIJLD/D NRRID NAME RKaras BHarris DSkeen DOorman DATE 06/27/14 06/27/14 07/03/14 07/17/14 OFFICIAL RECORD COPY