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Category:E-Mail
MONTHYEARML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) 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 ML23223A0142023-08-10010 August 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Exemption to 10 CFR 73.2, Physical Barriers 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 ML23135A0922023-05-11011 May 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Request to Use Specific Provision of a Later Edition of the ASME BPV Code, Section XI (L-2023-LLR-0016) 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) ML23073A0252023-03-13013 March 2023 NRR E-mail Capture - Fyi - Closeout the Evacuation Time Estimate (ETE) Reviews for SNC Fleet ML23045A0782023-02-13013 February 2023 NRR E-mail Capture - Fyi - Revised Estimated Hours - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML23009A0152023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR ML23009A0062023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR 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) ML22354A0112022-12-19019 December 2022 NRR E-mail Capture - Acceptance Review - Requested Licensing Action Regarding TS Revision to Adopt WCAP-17661-P-A, Improved Relaxed Axial Offset Control and Constant Axial Offset Control Fq Surveillance TS (L-2022-LLA-0148 and L-2022-LLA-01 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) ML22285A2532022-10-12012 October 2022 NRR E-mail Capture - Acceptance Review - Farley Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 ML22285A0082022-10-11011 October 2022 NRR E-mail Capture - Acceptance Review - Farley TS 4.3 LAR (L-2022-LLA-0138) ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22213A2692022-08-0101 August 2022 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specification 3.4.10, Pressurizer Safety Valves 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) ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22020A0662022-01-13013 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-269-A LAR (L-2021-LLA-0234) ML22012A0632022-01-11011 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TS 5.5.16 LAR (L-2021-LLA-0235) ML22010A2402022-01-10010 January 2022 NRR E-mail Capture - Farley 1 and 2 - Acceptance of Requested Licensing Action Revise TS 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure 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 ML21292A1562021-10-19019 October 2021 NRR E-mail Capture - Acceptance Review - SNC Operating Fleet TSTF-554 LAR ML21274A0462021-10-0101 October 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-577 LAR (L-2021-LLA-0163) ML21236A3142021-08-24024 August 2021 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Remove Sump Recirculation Valve Encapsulation ML21180A2002021-06-28028 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle - Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System (L-2021-LLA-0109) ML21174A1182021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet - Remove Table of Contents LAR (L-2021-LLA-0115) ML21174A1152021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle Exemption Requests from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (L-2021-LLE-0031) ML21132A0132021-05-11011 May 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet QATR Reduction in Commitment Licensing Action - L-2021-LLQ-0002 ML21105A0132021-04-14014 April 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet LAR to Change TS 5.7, High Radiation Area (L-2021-LLA-0052) 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) ML20318A0212020-11-12012 November 2020 NRR E-mail Capture - Fyi - Acceptance Review - SNC Fleet TSTF-541 LAR (L-2020-LLA-0232) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20289A1152020-10-0909 October 2020 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Requested Licensing Action Request for One-Time Exemption from 10 CFR 50, Appx E, Biennial EP Exercise Requirements Due to COVID-19 Pandemic NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20245E2842020-09-0101 September 2020 NRR E-mail Capture - Acceptance Review - SNC Fleet EP LAR (L-2020-LLA-0150 and L-220-LLA-151) ML20199M2572020-07-17017 July 2020 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20181A4072020-06-29029 June 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 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 NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request 2023-08-31
[Table view] Category:Inspection Plan
MONTHYEARML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) ML23335A0112023-12-0101 December 2023 IP 95001 Inspection Notification and Request for Information (EA-23-080) IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 ML22347A0882022-12-13013 December 2022 Final Farley Pi_R Initial RFI (2023) IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22101A2862022-04-0101 April 2022 RQ Inspection Corporate Notification Letter IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) ML20302A0002020-10-28028 October 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20175A1992020-06-23023 June 2020 Emergency Preparedness Program Inspection Request for Information ML20094H5182020-04-0303 April 2020 Plant Reference Simulator Inspection Request for Information IR 05000348/20190062020-03-0303 March 2020 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000348/2019006 and 05000364/2019006 ML19274D2092019-09-23023 September 2019 ISI Request for Information IR 05000348/20190052019-08-28028 August 2019 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Reports 05000348/2019005 and 05000364/2019005 IR 05000348/20190132019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 ML19100A0072019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000364/20180062019-03-0404 March 2019 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000346 and 05000364/2018006 ML19063B8902019-03-0404 March 2019 ISI Sgisi 2019002 RFI - Bcc ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18360A2312018-12-21021 December 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000348/20180052018-08-23023 August 2018 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Reports 05000348/2018005 and 05000364/2018005 ML18094A7822018-04-0303 April 2018 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2018011 and 05000364/2018011 ML18059A1532018-02-28028 February 2018 EOC Assessment Letter ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML18053A0942018-02-22022 February 2018 Baseline In-Service Inspection Initial Information Request ISI 2018002 Rpc IR 05000348/20170052017-08-28028 August 2017 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2, NRC Report 05000348/2017005 and 05000364/2017005 ML17156A1032017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000348/20160062017-03-0101 March 2017 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2016006 and 05000364/2016006) IR 05000348/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 - NRC Inspection Report 05000348/2016005 and 05000364/2016005 ML16244A3102016-08-29029 August 2016 Notification of Inspection and Request for Information ML16062A1522016-03-0202 March 2016 Final Annual Assessment Letter ML15260A9022015-09-17017 September 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2015005 and 05000364/2015005) ML14245A1752014-09-0202 September 2014 Mid-cycle Ltr 2014 ML14121A5042014-05-0101 May 2014 Notification of Triennial Fire Protection Baseline Inspection and Request for Information IR 050000348-14-009 and 05000364-14-009 IR 05000348/20140012014-03-0404 March 2014 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2014001 and 05000364/2014001) ML14063A1442014-03-0404 March 2014 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML13354B9722013-12-20020 December 2013 Notification of Joseph M. Farley Nuclear Plant, Units 1 and 2 Component Design Bases Inspection - NRC Inspection Report 05000348-14-007, 05000364-14-007 ML13253A3662013-09-10010 September 2013 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML13246A1102013-09-0303 September 2013 Mid-Cycle Assessment Letter ML13070A4622013-03-0808 March 2013 Notification of Inspection and Request for Information IR 05000348/20120012013-03-0404 March 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Unit 1 and Unit 2 (NRC Inspection Report 05000348/2012001 and 364/2012001) ML13015A3652013-01-15015 January 2013 Emerg Prep Insp and RFI for 2-18-2013 ML12248A0472012-09-0404 September 2012 Mid Cycle Assessment Letter Farley 2012 ML1124401732011-09-0101 September 2011 Report 22 - Farley ML1106301482011-03-0404 March 2011 Report 22, Inspection/Activity Plan 01/01/2011 - 06/30/2012 ML1024407102010-09-0101 September 2010 Report 22 2024-01-30
[Table view] 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] |
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Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request During the week of October 7 - October 11, 2019, the Nuclear Regulatory Commission (NRC) will perform the baseline in-service inspection at the Joseph M. Farley Nuclear Plant, Unit 1, in accordance with NRC inspection procedure IP 71111.08, Inservice Inspection Activities.
Experience has shown that this inspection is resource intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for information. Section A of the enclosure identifies information to be provided prior to the inspection to ensure adequate sample selection and preparation. Section B of the enclosure identifies additional information that the inspectors will need upon arrival at the site to complete the review of inspection samples. The inspection staff will appreciate if all the documents requested are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
We have discussed the schedule for this inspection activity with your staff and understand that our regulatory contact for this inspection will be Gene Surber of your organization. Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection, changes to the schedule of activities, or the material requested, please contact the lead inspector, Robert Carrion, at (404) 997-4522 or Robert.Carrion@nrc.gov.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading- rm/adams.html.
PAPERWORK REDUCTION ACT STATEMENT This document does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget under control numbers 3150-0008, 3150-0011, 3150-0014, 3150-0044, and 3150-0135.
PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement, unless the requesting document displays a currently valid Office of Management and Budget control number.
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request Document Request List Licensee: Joseph M. Farley Nuclear Plant, Unit 1 Docket No.: 50-348 Inspection Dates: October 7 - October 11, 2019 Entrance Meeting: October 7, 2019 Inspection Procedure: IP 71111.08, Inservice Inspection Activities, dated December 14, 2018 Inspectors: Robert Carrion, Senior Reactor Inspector (Lead Inspector) (ISI)
Brendan Collins, Reactor Inspector (SGISI)
A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office in care of the inspectors by September 27, 2019, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (compact disk, flash drive, etc.), or web-based document management system.
The inspectors will select specific samples from the information provided for items A.1 through A.5 below and then request additional documents needed for the onsite inspection week as described in Section B of this enclosure. The specific documents selected for Section B should be available and ready for review on the first day of inspection. If requested documents are large and only hardcopies are available, please inform the inspectors and provide the subject documentation during the first day of the onsite inspection. All documents requested in this section correspond to the unit scheduled to be in a refueling outage during the onsite inspection week, unless an information request item explicitly states that it applies to all operating units. In addition, some of the information requested may not apply to the site depending on the scope of refueling outage activities or other plant-specific conditions. If there are any questions regarding this information request, please contact the inspectors as soon as possible.
A.1 Non-destructive Examination and Welding Activities
- a. A detailed schedule (including preliminary dates) of nondestructive examinations (NDEs) planned for the structures, systems, and components (SSCs) listed below as part of the Inservice Inspection Program required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, as incorporated by reference in 10 CFR 50.55a, and other augmented in-service inspection activities:
- ASME Code Class 1, 2, and 3 components and supports (including Risk-Informed ISI
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request Program)
- ASME Code Class MC and metallic liners of Class CC components (e.g. reactor building containment liner)
- ASME Code Class MC supports
- Alloy 82/182/600 components (ASME Code Cases N-722-1 and N-770-1)
- Reactor vessel internals (e.g., Electric Power Research Institute (EPRI) MRP-227 Program)
- Other components to be inspected through NDE in accordance with industry initiatives or requirements (e.g. NEI-03-08 Initiatives or EPRI Guidelines)
- b. A detailed schedule (including preliminary dates) of welding activities to be completed on ASME Code Class 1, 2, or 3 components and supports during the upcoming refueling outage.
- c. A list of NDE reports (ultrasonic, radiographic, magnetic particle, and liquid penetrant) addressing surface or volumetric indications that were analytically evaluated and accepted for continued service in ASME Code Class 1, 2, and 3 components since the beginning of the last refueling outage. This list should also include any evaluations for continuous service performed as a result of Section XI pressure test(s) conducted during start up from the last refueling outage.
- d. A list of the welds in ASME Code Class 1, 2, and 3 systems that have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage. Please include a brief description of the welds such as system, material, pipe size, weld number, and NDEs performed. In addition, please indicate which of those welds are risk-significant.
- e. If NDE of pressure retaining welds in the reactor vessel shell required by the ASME BPVC,Section XI, Subsection IWB (also known as 10-year Reactor Vessel ISI) are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined and the extent of the planned examination. Please include reference numbers for applicable procedures that will be used to conduct these examinations.
- f. A copy of ASME BPVC,Section XI Relief Requests and the associated NRC Safety Evaluation Reports applicable to the NDEs scheduled for the upcoming refueling outage.
- g. A list of temporary Code or temporary non-Code repairs installed in ASME Code Class components (e.g., pinhole leaks or mechanical clamping devices).
- h. A copy of the most recent program self-assessments addressing the ISI Program and welding activities.
A.2 Reactor Pressure Vessel Upper Head Penetration (VUHP) Inspection Activities
- a. A detailed schedule (including preliminary dates) of NDEs planned for the reactor
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request pressure VUHPs to meet the requirements of ASME Code Case N-729-4, as incorporated by reference in 10 CFR 50.55a.
- b. A detailed scope of the planned NDEs for the reactor pressure VUHPs. Please identify the types of NDE methods to be used on each specific part of the vessel upper head to meet the augmented inspection requirements of ASME Code Case N-729-4, as incorporated by reference in 10 CFR 50.55a.
A.3 Boric Acid Corrosion Control Program (BACCP) Inspection Activities
- a. A copy of the procedures governing the implementation of the BACCP, including procedures required to identify boric acid leakage and perform boric acid leakage/corrosion evaluations.
- b. A list of leaks in ASME Code Class components which have been identified since the last refueling outage, including reference to the associated corrective action program documentation. If during the last cycle, the unit was shutdown, please provide documentation of containment walk-down inspections performed as part of the BACCP.
- c. Copy of the most recent self-assessment performed for the BACCP.
A.4 Steam Generator Tube Inspection Activities
- a. A detailed schedule of steam generator (SG) tube inspection, eddy current data analyses, tube in-situ pressure testing, tube repairs, and SG secondary side inspection activities for the upcoming refueling outage.
- b. A copy of the current version of the following documents:
- SG ISI Inspection Program and Plan
- Condition Monitoring Assessment
- c. A copy of the current Technical Specifications for the SG Inservice Inspection Program, including recent NRC Safety Evaluation Reports for license amendments issued since the last refueling outage (e.g. alternate repair criteria as a result of the incorporation of Technical Specification Task Force activities).
- d. Confirmation of whether SG primary-to-secondary leakage was identified and quantified during the previous operating cycle. If primary-to-secondary leakage was identified, please provide documentation describing the affected SG and corrective actions completed, or planned for this condition.
- e. A copy of the most recent Degradation Assessment.
- f. A copy of the Eddy Current Examination Plan describing the scope of SG tube examinations, including examination methods such as bobbin, rotating, or array
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request probes, and the percentage of tubes to be examined. Do not provide this information separately if it is already included in other documentation requested.
- g. A copy of the SG plant-specific degradation history provided to the vendor performing eddy current examination of the SG tubes during the upcoming outage.
Please include information on issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, and crud removal amounts, etc.). Do not provide this information separately if it is already included in other documentation requested.
- h. A copy of the following documents, as applicable:
- SG Eddy Current Data Analyst Guidelines
- Site-Validated Eddy Current Techniques
- Eddy Current Technique Qualification Records per EPRI Appendix H or I
- i. A copy of the most recent program self-assessments for SG tube integrity, loose parts monitoring, and secondary side water chemistry control.
- j. The location of the primary, secondary, and resolution analysis teams.
A.5 Other Information Related to All ISI Activities
- a. A list with a brief description of ISI-related issues entered into the corrective action program for all operating Units since the beginning of the last Unit 1 refueling outage, including issues related to the SG tube inspections and the BACCP. For example, provide a list of condition reports based upon database searches using keywords related to piping, vessels, and SG tube degradation such as: ISI, ASME Code,Section XI, NDE, welding, SG tube, reactor vessel, steam generator, reactor coolant system, crack, wear, thinning, leakage, thru-wall, rust, corrosion, boric acid, or errors in piping/SG tube examinations.
- b. A copy of the sites response to recent NRC generic communications and other industry operating experience notifications associated with the inservice inspection and structural integrity of ASME Code Class components issued since the beginning of the last refueling outage (e.g. Generic Letters, Information Notices, etc.).
- c. Names and contact information for the following program leads:
- ISI Program (examination, planning)
- Reactor Containment Building ISI Program
- Snubbers and Supports Inspection Program
- Repair and Replacement Program
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request
- d. Current outage and ISI program information including:
Current edition and addendum of the ASME Code being used for inspection, NDE, welding and repair/replacement activities Current edition and addendum of the ASME Code being used for containment inspections Outage name (e.g., U3R20)
Current ISI interval number, period within the interval, outage within the period and total number of outages overall for the interval (e.g. the first outage of the third period in the fourth interval of the ISI inspection program, and the fifth outage for the interval B. Information Requested for the Onsite Inspection Week Please provide the information requested below in hard copy or electronic (preferred) format to the inspectors at the entrance meeting, in order to finalize the planning of inspection activities onsite. Prior to the onsite inspection, the inspectors will select part of the inspection samples from the information provided in response to Section A of this enclosure, and then request additional information needed to complete the review.
There is a possibility that some of the inspection samples for which direct observation is desired (e.g., planned NDEs) will not be selected until the inspectors arrives onsite and confirms the current schedule of refueling outage activities for that week. All documents requested in this section correspond to the Unit scheduled to be in a refueling outage during the onsite inspection week, unless an information request item explicitly states that it applies to all operating Units. In addition, some of the information requested may not apply depending on the scope of refueling outage activities or other plant-specific conditions.
B.1 Non-destructive Examination Activities, Welding Activities, and Schedule Information
- a. Updated schedules for the planned NDE and welding activities described in the response to items A.1.a and A.1.b of this enclosure.
- b. For the NDEs selected by the inspectors from item A.1.a of this enclosure, please provide a copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, please provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Please include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
- c. For the NDE reports with relevant indications on ASME Code Class 1, 2, and 3 components selected by the inspectors from item A.1.c of this enclosure, please provide a copy of the examination records, NDE qualification records, and associated corrective action documents, including technical evaluations supporting the acceptability of the indications for continuous service.
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request
- d. For the ASME Code Class 1, 2, and 3 welds selected by the inspectors from item A.1.d of this enclosure, please provide copies of the following documentation for each subject weld:
- weld data sheet (traveler)
- weld configuration and supporting drawings (e.g., ISI isometric drawings)
- applicable ASME BPVC Edition and Addenda
- Weld Procedure Specification (WPS) used to fabricate the welds
- Procedure Qualification Records (PQRs) supporting the WPS
- mechanical test reports supporting the applicable PQRs
- welder performance qualifications records, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS
- examination records for the NDEs performed during weld fabrication
- personnel qualification records for both fabrication and preservice NDEs
- nonconformance reports for the selected welds (if applicable)
B.2 Reactor Pressure Vessel Upper Head Penetration (VUHP) Inspection Activities
- a. A copy of the latest calculation of effective degradation years (EDY) and re-inspection years (RIY) for the VUHP crack initiation and propagation susceptibility parameters.
- b. A copy of NDE reports from the last visual and non-visual VUHP examinations.
- c. If visual and/or non-visual NDEs of the VUHPs are planned for the upcoming refueling outage, please provide the following:
- a copy of the procedures governing the implementation of NDEs
- drawings showing the configuration of the VUHPs within the scope of the examinations (e.g. upper head insulation configuration, fabrication drawings of the nozzle attachments, geometrical limitations, etc.)
- documentation demonstrating the detection capability and qualification of the NDE personnel, procedures, and equipment in accordance with 10 CFR 50.55a
- identify any changes in equipment configurations used for the VUHPs examinations that differ from that used in the vendor qualification or demonstration report(s)
B.3 Boric Acid Corrosion Control Program Inspection Activities
- a. Inspection results for boric acid walk-downs, including an updated list of boric acid leaks identified during the current refueling outage with associated corrective action documentation, and overall status of planned boric acid inspections.
- b. A list of engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of corrective actions to repair and/or
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request clean these boric acid leaks. Please specify which known leaks, if any, have remained in service, or will remain in service, as active leaks.
- c. In accordance with NRC inspection procedure 71111.08, the inspectors would like to conduct an independent boric acid walk-down of the Reactor Building Containment early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspectors during the walk-down.
B.4 Steam Generator Tube Inspection Activities
- a. An updated schedule of SG tube inspection activities, including potential in-situ pressure tests, tube repairs, and secondary side inspections.
- b. A copy of the Eddy Current Examination Technique Specification Sheets from the EPRI Performance Demonstration Database that are applicable to the scheduled examinations of SG tubes.
- c. A copy of the eddy current examination procedures governing the SG tube examination activities. Specifically, provide the procedures for calibration, flaw detection, and flaw sizing.
- d. Access to the training and qualification records of personnel performing eddy current data analysis, including training material and test results for any site-specific training provided to the data analysts.
- e. Access to the certification records of eddy current equipment (i.e., eddy current instruments, probes, and calibration standards).
- f. A copy of the procedures to be followed if a loose part or foreign material is identified in the steam generators.
- g. Documentation demonstrating that the in-situ pressure test screening criteria are in accordance with the applicable EPRI Guidelines. Please have knowledgeable staff available to discuss the analytical method used to determine the in-situ pressure test screening criteria.
- h. A list of corrective action documents generated by the vendor with respect to SG tube inspection activities during the current refueling outage.
B.5 Other Information Related to All ISI Activities
- a. For the ISI-related corrective action issues selected by the inspectors from item A.5.a of this enclosure, please provide copies of the corrective action documents and supporting documentation (e.g., cause evaluations, work orders, corrective action plan, etc.).
- b. An updated list of ISI-related issues entered into the corrective action program for the current refueling outage, including issues related to the steam generator tube inspections and Boric Acid Corrosion Control Program.
Joseph M. Farley Nuclear Plant, Unit 1 Baseline In-Service Inspection Initial Information Request
- c. A copy of or ready access to:
- applicable editions and sections of the ASME BPVC (e.g., Sections II, III, V, IX, and XI) for the inservice inspection and repair/replacement activities selected for review
- industry standards referenced in the procedures for the BACCP
- a current revision of the ISI Program Manual and Plan for the current interval Inspector Contact Information:
Robert Carrion Brendan Collins Senior Reactor Inspector Reactor Inspector Engineering Branch 3 Engineering Branch 3 Division of Reactor Safety Division of Reactor Safety 404-997-4522 404-997-4420 Mailing Address:
US NRC Region II Attn: Robert Carrion 245 Peachtree Center Avenue, Suite 1200 Atlanta, GA 30303
From: Carrion, Robert To: Egelstad, Donna
Subject:
FW: Request for Information for October ISI of Unit 1 Date: Wednesday, August 07, 2019 2:55:51 PM Attachments: Farley U1 RFI ISI 2019004 RPC.docx Hello, Donna.
I am forwarding the e-mail, including the attachment, for the Farley ISI Request for Information. Please give it an ML number to make it an official document on the docket.
Thank you.
Bob Carrion From: Carrion, Robert Sent: Wednesday, August 07, 2019 7:42 AM To: Surber, Ronnie Gene <RGSURBER@SOUTHERNCO.COM>
Cc: Champion, Sarah C. <SCCHAMPI@southernco.com>
Subject:
Request for Information for October ISI of Unit 1 Hello, Gene.
Attached is our Request for Information for the upcoming Unit 1 ISI. As requested, I cced Dee Dee.
If you have any questions/comments, please contact me at your earliest convenience.
Thank you, Bob Carrion 404-997-4522