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| ==Enclosure:== | | ==Enclosure:== |
| * Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC LPL2-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource JRobinson, NRR LFields, NRR RGallucci, NRR ADAMS Accession No.: ML14176A070 OFFICE LPL2-1/PM . LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 07/01/14 06/30/14 07/11/14 07/11/14 OFFICIAL RECORD COPY}} | | PUBLIC LPL2-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource JRobinson, NRR LFields, NRR RGallucci, NRR ADAMS Accession No.: ML14176A070 OFFICE LPL2-1/PM . LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 07/01/14 06/30/14 07/11/14 07/11/14 OFFICIAL RECORD COPY}} |
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MONTHYEARNL-12-1893, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2012-09-25025 September 2012 License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request ML12345A3982012-12-12012 December 2012 Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742)(NL-12-1893) Project stage: Acceptance Review NL-12-2566, Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2012-12-20020 December 2012 Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML13022A1582013-01-24024 January 2013 Acceptance Review Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (N-1-2-1893) Project stage: Acceptance Review ML13050A2862013-02-22022 February 2013 3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology Project stage: RAI ML13067A2692013-03-11011 March 2013 03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Meeting ML13176A0932013-07-0808 July 2013 Request for Additional Information Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (NL-12-1893) Project stage: RAI ML14038A0192013-09-16016 September 2013 Joseph M. Farley, Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generati Project stage: Request NL-13-2039, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-10-30030 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-13-2269, Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-11-12012 November 2013 Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML14066A0472014-03-0707 March 2014 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742 Project stage: Draft RAI ML14073A0532014-03-28028 March 2014 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML14114A5502014-04-23023 April 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0733, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-05-23023 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0927, Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 32014-07-0303 July 2014 Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 3 Project stage: Response to RAI ML14176A0702014-07-11011 July 2014 Request for Additional Information Project stage: RAI NL-14-1106, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants2014-08-11011 August 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants Project stage: Response to RAI NL-14-1273, Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants2014-08-29029 August 2014 Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants Project stage: Response to RAI NL-14-1937, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2015-01-16016 January 2015 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML15023A0522015-01-23023 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Request ML15043A4592015-02-24024 February 2015 Summary of Site Audit to Support the Review of a License Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2, to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis Project stage: Approval ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) Project stage: Approval 2014-03-28
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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:Request for Additional Information (RAI)
MONTHYEARML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate ML20055E9752020-02-28028 February 2020 Request for Additional Information Update the Spent Fuel Pool Criticality Safety Analysis (EPID L-2019-LLA-0212) Non-Proprietary Version ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) ML19066A0422019-03-0707 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 ML19056A2142019-02-25025 February 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18239A1542018-08-24024 August 2018 Emergency Preparedness Inspection and Request for Information ML18087A1462018-05-0101 May 2018 Request for Additional Information TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 ML17010A0142017-01-19019 January 2017 Request for Additional Information Regarding License Aging Management Program ML16243A1992016-08-30030 August 2016 Notification of Inspection and Request for Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16204A0422016-07-26026 July 2016 Acceptance Letter, Unacceptable, with Opportunity to Supplement ML16187A3082016-06-28028 June 2016 Requalification Program Inspection - Joseph M. Farley Nuclear Plant 2024-01-12
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 2014 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, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME9741 AND ME9742)
Dear Mr. Pierce:
By letter dated September 25, 2012 (Agencywide Documents Access and Management System Accession No. ML12279A235), the Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request (LAR) for Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2~ The LAR would permit transition of the fire protection licensing basis from Title 10 of the Code of Federal Regulations, Section 50.48(b), to 10 CFR 50.48(c), "National Fire Protection Association Standard NFPA 805."
The Nuclear Regulatory Commission staff has determined that additional information is needed as discussed in the Enclosure. We request that SNC respond within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv ,
)
REQUEST FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS DOCKET NOS. 50-348 AND 50-364 By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12279A235), as supplemented by letter dated October 30, 2013 (ADAMS Accession No. ML13305A105), Southern Nuclear Company (SNC) requested an amendment to, the Technical Specifications for the Joseph M. Farley Nuclear Plant (Farley).
Specifically, the requested change would allow the licensee to adopt National Fire Protection Association Standard 805, "Performance-Based Standard for Fire Protection for Light Water
. Reactor Generating Plants."
Section 2.4.3.3 of NFPA 805 states that the Probabilistic Risk Assessment approach, methods,
- and data shall be acceptable to the NRC. Section 2.4.4.1 of NFPA-805 further states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174 provides quantitative guidelines on core damage frequency, large early release frequency, and identifies acceptable changes to these frequencies that result from proposed changes to the plant's licensing basis and describes a general framework to determine the acceptability* of risk-informed changes. The U.S. Nuclear Regulatory Commission (NRC) staff has identified additional information that is required to fully characterize the risk estimates. *
.PRA RAI 16.a.02 In a letter dated May 23, 2014, (ADAMS Accession No. ML14147A368) the licensee responded to PRA 16.a.01 citing planned enhancement of operations guidance for controlling fires in the main control board (MCB) panels prior to the assumed damage time of 10 minutes for sensitive
/.
electronics. Describe if there is an implementation item to Attachment S that addresses the development and implementation of this procedure. If not, describe the method that will be used to ensure development of the procedure.
PRA RAI 35.01 In the submittal dated September 25, *2012, a reference to the Fire PRA Logic Model (App. B on page B-1) states that Farley Unit 1 installed the new Westinghouse Shutdown Shield (SDS) in fall 2010. The internal events PRA, upon which the Fire PRA is based, takes credit for the SDS (failure probability of 0.0271/demand), limiting the leakage rate to 2 gpm where the faces of the Enclosure
)
/
SDS seal components remain in contact. The assumed leakage rate is increased to 19 gpm if the SDS actuates but the pump shaft continues to rotate if not tripped in a timely manner.
Finally, if the SDS does not actuate at all, "existing" seal model leakage rates are applied as stated in WCAP-15603, Rev. 1-A, (Non-Proprietary) 'WOG 2000 Reactor Coolant Pump Seal Leakage Model for Westinghouse PWRs" (MUMP-6074) (ADAMS Accession No.
M~032040132). Based on the July 26, 2013, Part 21 issuance by Westinghouse concerning defects with the SDS performance, discuss if there have been any new developments regarding, the status of the SDS performance. If the licensee is still planning to take credit for an upgraded SDS:
- a. Provide relevant information from technical design documents, testing evaluations, draft topical reports, etc., that support the incorporation and quantification of the SDS performance in the Farley Fire PRA model. As appropriate, justify any assumptions for
- new risk reduction credit or retention of credit previously assumed in and consistent with Final Safety Evaluation For Pressurized Water Reactor Owners Group Topical Report WCAP-17100-P/Np, Revision 1, "PRA Model For The Westinghouse Shut Down Seal,"*
PA-RMSC-0499 (ADAMS Accession No. ML110880526), or other NRC endorsed technical bases.
- b. If the credit is dependent upon plant operational experience with the upgraded SDS, discuss to what extent credit can and will be taken prior to installation/upgrade and completion of any required operational duration necessary to justify such credit.
- c. If an alternative to the SDS is planned, provide the analogous information to the above for the alternative.
- d. Describe if there is an implementation item to Table S-3 that will identify when a confirmatory evaluation of the achieved NFPA-805 transition risk and changes in risk (that includes when the installed and tested seals) will be completed: Include what change in risk guidance will be used to determine any required actions, and what actions will be required to complement this new implementation item. If there is no new implementation item, describe the method that will be used to report the confirmatory evaluation activities listed above.
- PRA RAI36 Provide the results of a composite analysis that shows the integrated impact on the fire risk (core damage frequency (CDF), larger early release frequency (LERF), change in (~)CDF,
~LERF) after replacing all the identified methods and weaknesses. As the review process is concluded, additional changes to replace any method or weakness still under review may be required. In this composite analysis, for those cases where the individual issues have a synergistic impact on the results, a simultaneous analysis must be performed, specifically for those items listed below.
For cases where no synergy exists, a one-at-a-time analysis may be done. If the impact on the change in risk from transition is negligible, a quantitative evaluation is unnecessary.
- a. The results from the analysis for PRA RAI 35.01 above.
- b. In the LAR submittal dated September 12, 2012, and the LAR supplement gated December 20, 2012, sensitivities related to the electrical cabinet fire severity method (Section V.2.1) and use of control power transformer (CPT) (Section V.2.3; also response to PRA RAI 08.a).
- c. In the letter dated September 16, 2013 (ADAMS Accession No. ML14038A019) containing the following RAI responses:
- PRA RAI 15.a - Revised seismic CDF based on 2008 United States Geological Survey (USGS) data, and
- PRA RAI 28.k- Validity of current ignition bin 15 fire frequencies.
- d. In the letter dated November 12, 2013 (ADAMS Accession No. ML13318A027) containing the following RAI responses:
- PRA RAI 17.d- turbine building collapse, and
- PRA RAI 33.c- Revised main control room (MCR) abandonment analysis (also RAI PRA 33.c.01). (incorporates PRA RAI 07.e- Use of 0.1 CCDP for MCR abandonment)
- e. Fire Modeling (FM) RAI responses from letters dated September 16, 2013 (ADAMS Accession ML14038A017 and ML14038A019), October 30, 2013 (ADAMS Accession No. ML13305A105), November 12, 2013 (ADAMS Accession No. ML13318A027), and April 23, 2014 (ADAMS Accession No. ML14114A550):
- FM RAI 01.b- Use of FAQ 08-0052 Recommended or Shorter Fire Growth Rates for MCR Abandonment Analysis,
- FM RAI 01.c- Use of Society of Fire Protection Engineers (SFPE) Handbook Heats of Combustion for Teflon and Tefzel in MCR Abandonment Analysis,
- FM RAI 01.d- Update of MCR Abandonment Analysis for Wall and Corner Effects forTransient Fires, *
- FM RAI 01.h- Development of new zone of influence (ZOI) Tables for,Generic Fire Modeling Treatments,
- FM RAI 01.i - Use of New hot gas layer (HGL) Tables in Generic Fire Modeling Treatments Involving Secondary Combustibles, and
- FM RAI 08- Assumption of Instantaneous Peak heat release rates (HRR) for Fires in Medium Voltage switchgear (SWGR) following a high energy arcing fault.
July 11, 2014 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, UNIT NOS. 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME9741 AND ME9742)
Dear Mr. Pierce:
By letter dated September 25, 2012 (Agencywide Documents Access and Management System Accession No. ML12279A235), the Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request (LAR) for Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2. The LAR would permit transition of the fire protection licensing basis from Title 10 ofthe Code of Federal Regulations, Section 50.48(b), to 10 CFR 50.48(c), "National Fire Protection Association Standard NFPA 805."
The Nuclear Regulatory Commission staff has determined that additional information is needed as discussed in the Enclosure. We request that SNC respond within 30 days of the date of this letter. Please note thatthe NRC staff's review is continuing and further requests for information may be developed.
Sincerely,
/RAJ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsRgn2MaiiCenter Resource RidsNrrLASFigueroa Resource RidsNrrDe Resource RidsNrrPMFarley Resource JRobinson, NRR LFields, NRR RGallucci, NRR ADAMS Accession No.: ML14176A070 OFFICE LPL2-1/PM . LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 07/01/14 06/30/14 07/11/14 07/11/14 OFFICIAL RECORD COPY