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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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OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 25, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - TRANSMITTAL OF U.S. ARMY CORPS OF ENGINEERS FLOOD HAZARD REEVALUATION INFORMATION (TAC NOS. MF3037 AND MF3038)
Dear Mr. Pierce:
The purpose of this letter is to transmit the U.S. Army Corps of Engineers (USAGE) portion of the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley) flood hazard reevaluation (FHR) associated with the assessment of flood hazards due to flooding in streams and rivers, including potential site flooding due to dam failure. By letter dated September 26, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13274A343),
Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested assistance from the U.S. Nuclear Regulatory Commission (NRG) in obtaining information from the USAGE to support SNC's development of a report documenting the FHR in response to the March 12, 2012, request for information (ADAMS Accession No. ML12073A348). The NRG staff held meetings to discuss the details of the information being provided by USAGE with SNC and the USAGE on the following dates:
These meetings were closed to the public due to the discussion of security-related information.
The licensee supplemented its September 26, 2013 letter, requesting details from the USAGE by letters dated May 6, 2014 (ADAMS Accession No. ML14127A178), and March 13, 2015 (ADAMS Accession No. ML15084A588) as a result of the discussions at these meetings.
By letter dated February 28, 2014 (ADAMS Accession No. ML14072A486), SNC requested permission to submit its report documenting the FHR 120 days after receipt of the information from the USAGE. The NRG staff held a public meeting on May 16, 2014 to discuss the extension (summary can be found at ADAMS Accession No. ML14134A031). By letter dated May 21, 2014 (ADAMS Accession No. ML14141A629), SNC provided a supplement to this request that addressed site-specific information requested by the NRG staff. Following receipt of this supplement, by letter dated July 17, 2014 (ADAMS Accession No. ML14174A938), the NRG staff approved SNC's request to submit the report documenting the FHR at the Farley site 120 days after receipt of the USAGE information.
Enclosures 1, 2, and 3 to this letter contain Security-Related Information. When separated from the enclosures, this letter is DECONTROLLED.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION G. Pierce In addition, the July 17, 2014, letter states that if the USAGE results show that the design-basis flood levels at the Farley site are exceeded by the flood levels resulting from the FHR, SNG must submit its planned interim actions to address the higher flood level to the NRG within 60 days of receipt of the USAGE information.
The enclosures to this letter contain the following: (1) a brief description of the enclosed files; (2) summary tables of the results; and (3) the results of the USAGE FHR developed in accordance with Japan Lessons-Learned Directorate (JLD) interim staff guidance (ISG)
JLD-ISG-2013-01, "Interim Staff Guidance For Assessment of Flooding Hazards Due to Dam Failure," Revision 0, dated July 29, 2013 (ADAMS Accession No. ML13151A153). Enclosure 2 contains the relevant USAGE results at Farley, which SNG needs to consider as part of their flood hazard evaluation report. The USAGE results are based on the guidance JLD-ISG-2013-01 and on the USAGE knowledge of the river system. Enclosure 3 is a DVD containing the results at the river mile locations SNG requested as documented in the September 26, 2013, letter and supplemented by the May 6, 2014, and March 13, 2015, letters. The USAGE results contained in Enclosure 2 are a subset of the information contained in Enclosure 3.
If you have any questions, please contact me at (301) 415-6185 or by e-mail at Anthony.Minarik@nrc.gov or Juan Uribe at (301) 415-3809 or by e-mail at Juan.Uribe@nrc.gov.
Sincerely, Anth ny . Minarik.e::ger Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosures:
- 1. Brief Description of Transmitted Documents
- 2. USAGE FHR plots
- 3. DVD containing USAGE FHR spreadsheets cc w/o encls: Distribution via Listserv OFFICIAL USE ONLY SECURITY RELATED INFORMATION
ML13151A153). Enclosure 2 contains the relevant USAGE results at Farley, which SNG needs to consider as part of their flood hazard evaluation report. The USAGE results are based on the guidance JLD-ISG-2013-01 and on the USAGE knowledge of the river system. Enclosure 3 is a DVD containing the results at the river mile locations SNG requested as documented in the September 26, 2013, letter and supplemented by the May 6, 2014, and March 13, 2015, letters. The USAGE results contained in Enclosure 2 are a subset of the information contained in Enclosure 3.
If you have any questions, please contact me at (301) 415-6185 or by e-mail at Anthony.Minarik@nrc.gov or Juan Uribe at (301) 415-3809 or by e-mail at Juan.Uribe@nrc.gov.
Sincerely, IRA/
Anthony J. Minarik, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 DISTRIBUTION:
PUBLIC (LETTER ONLY) RidsNsirDspRsps Resource MShams, NRR/JLD JHMB R/F RidsRgn2MailCenter Resource SSandal, RIV/DRP RidsAcrsAcnw_MailCTR Resource BHarvey, NRO/DSEA/RHEB KSee, NRO/DSEA/RHEB RidsNrrDorlLpl2-1 Resource CCook, NRO/DSEA/RHEB ACampbell NRO/DSEA RidsNrrLASLent Resource KMiller, Rll/DRP AMinarik, NRR/JLD RidsNrrPMFarley Resource PNiebaum, Rll/DRP ADAMS Accession Nos.: Pkg: ML15168A755; Redacted Letter: ML151768199; OUO-SRI Letter: ML15168A803; Enclosure 1: ML15176A237; Enclosure 2: ML15176A536, ML15176A545, ML15176A549
- via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME AMinarik SLent MShams DATE 06/18/15 06/18/15 06/19/15 OFFICE NRO/DSEA/RHEB/BC* NRR/JLD/JHMB/PM NAME CCook AMinarik DATE 06/24/15 06/25/15