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| | number = ML12088A207 | | | number = ML12088A207 |
| | issue date = 04/04/2012 | | | issue date = 04/04/2012 |
| | title = Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information (TAC Nos. ME7094 and ME7095) | | | title = Request for Additional Information |
| | author name = Martin R E | | | author name = Martin R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Ajluni M J | | | addressee name = Ajluni M |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
| | license number = NPF-002, NPF-008 | | | license number = NPF-002, NPF-008 |
| | contact person = Martin R E | | | contact person = Martin R |
| | case reference number = TAC ME7094, TAC ME7095 | | | case reference number = TAC ME7094, TAC ME7095 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) Dear Mr. Ajluni: By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, 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 cc w/encl: Distribution via Listserv REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1. The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it. On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit. The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports." | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) Dear Mr. Ajluni: By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML 112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. Please provide your response to the request for additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, 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 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207 RULPL2-1/PM SS/SNPB/BC | | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| * B memo dated DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy
| | |
| }} | | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) |
| | |
| | ==Dear Mr. Ajluni:== |
| | |
| | By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. |
| | Please provide your response to the request for additional information within thirty (30) days of the date of this letter. |
| | Sincerely, Robert E. Martin, 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 cc w/encl: Distribution via Listserv |
| | |
| | REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1. |
| | RAI-01: The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it. |
| | RAI-02: On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit. |
| | RAI-03: The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] |
| | 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports." |
| | |
| | April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095) |
| | |
| | ==Dear Mr. Ajluni:== |
| | |
| | By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure. |
| | Please provide your response to the request for additional information within thirty (30) days of the date of this letter. |
| | Sincerely, IRA! |
| | Robert E. Martin, 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 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207 |
| | * B memo dated RULPL2-1/PM DORULPL2 SS/SNPB/BC DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy}} |
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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 April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095)
Dear Mr. Ajluni:
By letter dated September 9,2011 (Agencywide Documents Access and Management System Accession No. ML112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure.
Please provide your response to the request for additional information within thirty (30) days of the date of this letter.
Sincerely, Robert E. Martin, 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 cc w/encl: Distribution via Listserv
REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 "LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION TABLE 3.3.1-1" SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 TAC NOS. ME7094 AND ME7095 The following is a listing of comments, questions, and clarifications noted during the initial review of the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 License Amendment Request (LAR) for Technical Specification (TS) Table 3.3.1-1.
RAI-01: The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it.
RAI-02: On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure Signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit.
RAI-03: The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement]
3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports."
April 4, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7094 AND ME7095)
Dear Mr. Ajluni:
By letter dated September 9, 2011 (Agencywide Documents Access and Management System Accession No. ML112521438), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request regarding Joseph M. Farley Nuclear Plant, Units 1 and 2, to add Surveillance Requirement 3.3.1.14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." The U.S. Nuclear Regulatory Commission is reviewing your application and finds that additional information on the nuclear performance and codes review aspects of your application is needed as set forth in the enclosure.
Please provide your response to the request for additional information within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, 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 cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource KHeller, NRR RidsNrrDssStsb Resource RidsNrrPMFarley Resource RidsNrrDeEicb Resource RAlvarado, NRR ADAMS Accession No.: ML12088A207
- B memo dated RULPL2-1/PM DORULPL2 SS/SNPB/BC DORULPL2-1/BC DORULPL2-1/PM SFigueroa NSalgado RMartin 03/29/12 102/12 04/04/12 04/04/12 OFFICIAL RECORD COpy