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Category:Inspection Plan
MONTHYEARIR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000348/20230062024-02-28028 February 2024 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2023006 and 05000364/2023006 ML24037A1362024-02-0606 February 2024 RP DLR Feb. 2024 ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML23335A0112023-12-0101 December 2023 IP 95001 Inspection Notification and Request for Information (EA-23-080) ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) 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 ML19100A0072019-04-10010 April 2019 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000348/2019013; 05000364/201901 IR 05000348/20190132019-04-10010 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 ML14063A1442014-03-0404 March 2014 2013 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 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) 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) 2024-08-26
[Table view] Category:Letter
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24271A0052024-09-26026 September 2024 NRR E-mail Capture - for Your Response - RAI - Farley and Vogtle 1 and 2 - Proposed Alternative Request for Steam Generator Welds (L-2024-LLR-0041) ML24227A0512024-08-14014 August 2024 August 14, 2024 - Request for Additional Information - Farley, Units 1 and 2 - Proposed LAR to Revise TS SR 3.6.6.8 Frequency ML24179A1242024-06-27027 June 2024 ISFSI Request for Information (2024) ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions ML24037A1362024-02-0606 February 2024 RP DLR Feb. 2024 ML24037A1352024-02-0505 February 2024 e-mail ML23341A2042024-01-12012 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 ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 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 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 2024-09-26
[Table view] |
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Farley Nuclear Plant Radiation Safety Baseline Inspection Initial Information Request Inspection Report: 2018-002 During the weeks of April 9 - 13 and May 7 - 11, 2018, the NRC will perform a baseline Radiation Safety Inspection at Farley Nuclear Plant, Units 1 and 2 (NRC Inspection Procedures 71124.01, 71124.02, 71124.03, 71124.04, 71124.05, and 71151). 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 are requesting in advance documents needed for this activity. It is important that all of these documents are up-to-date, and complete, thereby minimizing the number of additional documents requested during the preparation, and/or the onsite portions of the inspection. The NRC requests that these documents be provided to the inspectors no later than March 29, 2018.
If there are any questions about this inspection or the material requested, please contact the lead inspector, Jonathan Rivera at 404-997-4508, or the Plant Support Branch 1 Chief, Brian Bonser at 404-997-4653.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, a copy of this document will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/readingrm/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.
Enclosure
Document Request List Inspection Dates: April 9 - 13 and May 7 - 11, 2018 Documents Due to Region II by: March 29, 2018 Inspection Procedures (IPs): 71124.01 Radiological Hazard Assessment and Exposure Controls 71124.02 Occupational ALARA Planning and Controls 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 71124.04 Occupational Dose Assessment 71124.05 Radiation Monitoring Instrumentation 71151 Performance Indicator Verification Lead Inspector: Jonathan Rivera Health Physicist U.S. NRC Region II 404-997-4646 Jonathan.Rivera@nrc.gov Note: The current version of these documents is expected unless specified otherwise.
Electronic media is preferred if readily available. [Note that the inspectors cannot accept data provided on USB or flash drives due to NRC IT security policies.] Please organize the information as it is arranged below to the extent possible. Experience has shown that a poorly organized CD leads to a less efficient inspection, and places additional burden on licensee staff.
Pay particular attention to the date ranges for the items requested as they may change from item to item. If there are questions regarding the documents requested, or if the documents cannot be provided by the due date, please do not hesitate to contact the lead inspector.
General and Miscellaneous Information
- List of primary site contact(s) for each inspection area including name(s) and telephone numbers.
- Plant Management, Radiation Protection, and Chemistry organizational charts with contact numbers.
Enclosure
- Outage schedule, including work activities to be conducted during the week(s) of the inspection.
- Audits and self-assessments performed since October 1, 2016 that encompass each of the inspection areas below.
71124.01 - Radiological Hazard Assessment and Exposure Controls (Last inspected October 2017)
- 1. List of active RWPs, including outage RWPs, with their administrative limits, electronic dosimeter dose rate limits, and dose limits.
- 2. List of locations, or plant maps indicating the location, of all LHRAs and VHRAs. Include areas with the potential to become a LHRA during routine operations or outages.
- 3. ISFSI information to include surveys, exposure data, ALARA planning and reviews conducted for the last two moves. Also, the last two routine surveys of the facility and any TLD area monitoring results of the facility.
- 4. Procedures related to HP controls (e.g. posting, labeling, surveys, RWPs, contamination control, HRA/LHRA/VHRA control, key control, control of divers, special controls during fuel offload, hot spots, etc.).
- 5. Procedures related to release of personnel and materials (e.g. release surveys, decontamination, guidance for alarm follow up, etc.).
- 6. List of Nationally Tracked Sources, change of ownership and copies of any NSTS transaction documentation (e.g., annual reconciliation).
- 7. Most recent sealed source inventory record.
- 8. List of all non-fuel items stored in the SFP(s).
- 9. List of CAP documents (e.g. NCRs, CRs, etc.) related to HP controls, including any human performance errors by radworkers and HP technicians, generated since October 1, 2017. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.
- 10. All CRs generated related to Nationally Tracked Sources since October 1, 2017.
71124.02 - ALARA Planning and Controls (Last inspected October 2016)
- 1. Site and corporate procedures associated with maintaining site dose ALARA, including those involving ALARA work activities. These procedures should include:
- ALARA program implementation, including ALARA committee activities and ALARA planning, briefing, and reviews.
- RWP preparation and worker compliance.
- Processes used to estimate and track exposures for specific work activity.
- Making changes to dose estimates during task performance.
- Exposure mitigation requirements.
- 2. List of top five dose jobs for the upcoming refueling outage and ALARA planning packages (including dose estimates, work-hour estimates, special HP controls, and dose reduction initiatives).
- 3. Most recent annual ALARA report and most recent refueling outage report.
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- 4. ALARA Committee activity summaries (e.g. meeting minutes) discussing and approval of activities associated with the upcoming refueling outage.
- 5. Outline of the source term reduction strategy. Information should include:
- Historic trends and current status of plant source term.
- Factors that affect the source term.
- Activities employed to reduce the source term.
- Specific sources identified for reduction actions.
- Source term reduction evaluation.
- Results achieved since October 1, 2016.
- 6. List of CAP documents (e.g. NCRs, CRs, etc.) generated since October 1, 2016, related to the ALARA program, including the following [This should be a list of corrective action documents containing a CR number and brief description, not full CRs]:
- Post-job review identified problems.
- Radiation worker practices.
- Occurrences where the collective exposure was greater than intended dose determined to be ALARA for the individual work activities.
- 7. Available for onsite review during the inspection:
- ALARA planning packages for jobs to be performed during the outage.
- Temporary shielding requests generated for the outage.
- Completed ALARA packages (including post-job reviews) for the five work activities that were completed during the last outage that had the greatest collective dose, and/or presented significant radiological risk.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation (Last inspected October 2016)
- 1. Site and corporate procedures associated with airborne radiation monitoring instrumentation and respiratory protection. Procedures/manuals should include:
- Operation, calibration, and maintenance of air sampling instrumentation, including set-point determination (e.g., low-vols, high vols, goosenecks, AMS 4s, etc.).
- Actions to be taken when air sampling instrumentation is found to be significantly out of tolerance/calibration.
- Issuance and use of respiratory protective equipment (emphasis on SCBA and air-supplied equipment).
- Total Effective Dose Equivalent-ALARA evaluation guidance.
- Training, including fit-testing, for use of SCBA and supplied-air systems.
- SCBA maintenance activities, including vital components (i.e. regulators).
- Determination/verification of Grade D air for SCBAs.
- 2. Two most recent HEPA filter DOP and charcoal test results of the following ventilation systems:
- 3. Records of certification of air quality for equipment used to provide breathing air for air-supplied respirators and SCBA bottles (air compressors and bottled breathing air) since October 1, 2016.
- 4. Documentation for last two surveillances performed on SCBAs stored for emergency use.
- 5. List of CAP documents (e.g. NCRs, CRs, etc.) generated since October 1, 2016 4
involving airborne radioactivity monitoring and respiratory protective equipment deficiencies. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.
- 6. Available for onsite review during the inspection:
- Inventory, inspection, and maintenance records for SCBA equipment.
- Training records, including fit-testing, for SCBA-qualified individuals, including:
- i. List of all licensed operators qualified to use SCBAs.
ii. List of all instrumentation and control personnel qualified to use SCBAs.
iii. List of all HP personnel qualified to use SCBAs.
- Training records/certification for individuals qualified to perform maintenance on vital components (e.g. regulators) on SCBAs.
71124.04: Occupational Dose Assessment (Last inspected October 2016)
- 1. Site and corporate procedures associated with occupational dose monitoring, including multi-badging and monitoring in highly variable dose rate gradients, PCEs, storage and care of personal dosimeters, use of electronic dosimeters including evaluation of any biases identified relative to TLD monitoring, internal dose assessment (i.e., both in vivo and in vitro bioassay and air sampling capabilities, and calibration/QC and use of the WBC), release of contaminated individuals, use of passive monitoring, and actions for DPWs.
- 2. NVLAP accreditation documentation for current dosimetry used by the site.
- 3. List of all positive whole body counts, and in vitro or air sampling analyses which resulted in an assigned CEDE equal to, or exceeding, 10 millirem since October 1, 2016.
[Note: only a listing should be provided for use by the inspectors to select a sample of issues for in-depth review during the onsite inspection].
- 4. List of all PCEs identified since October 1, 2016. [Note: only a listing should be provided for use by the inspectors to select a sample of issues for in-depth review during the onsite inspection].
- 5. List of CAP documents (e.g. NCRs, CRs, etc.) generated since October 1, 2016 associated with internal and external dosimetry. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.
71124.05 - Radiation Monitoring Instrumentation (Last inspected October 2016)
- 1. Site and corporate procedures associated with:
- use of portable instrument calibrators (e.g. Shepherd calibrator).
- calibration and functional test/source checks of portable radiation detection instrumentation.
- QA program for count room instruments (e.g. laboratory inter-comparison data).
- 2. The last two calibration records for the following monitors:
- U1 Containment Area Radiation Monitor (R-2)
- U2 Fuel Handling Area Radiation Monitor (R5)
- U1 Control Room Area Radiation Monitor (R1)
- U2 Charging Pump Room Area Radiation Monitor (R4) 5
- 3. Documentation for the radioactive sources used to calibrate the instruments in item 2 above, including paperwork showing traceability to a NIST standard and/or traceability to the primary calibration, as applicable.
- 4. The last two surveillances performed on the Post-accident Sampling System, as applicable if it is still required in the plant technical specifications
- 5. The last two test records of the instrument calibrator (Shepherd validation testing/dose rate curves).
- 6. The last two calibration records of the WBC.
- 7. List of the following radiation monitors currently in service. Several will be selected for on-site review of the calibration records:
- PMs used in Dosimetry for Passive Monitoring.
- Count room High-purity Germanium and liquid scintillation systems.
- 8. Documentation for the radioactive sources used to calibrate the monitors requested for item 8 above showing NIST standard.
- 9. Chart or procedure listing any EAL values associated with installed or portable radiation monitoring instrument indication(s).
- 10. List of CAP documents (e.g. NCRs, CRs, etc.) generated since October 1, 2016, related to portable and fixed instrumentation, including PMs, PCMs, SAMs, WBC, ARMs, CAMS, and count room instruments. This should be a list of corrective action documents containing a CR number and brief description, not full CRs.
71151 - Performance Indicator (PI) Verification (Last inspected August 2017)
- 1. Site and corporate procedures for gathering and reporting PI data.
- 2. List of all CAP documents since August 1, 2017, using keywords such as: HRA, LHRA, VHRA, unintended dose, unlocked door, etc.
- 3. List of all ED dose rate alarms and ED dose alarms since August 1, 2017, that includes dose or dose rate alarm received, and the alarm setpoint(s).
- 4. List of all CAP documents (e.g. NCRs, CRs, etc.) generated since August 1, 2017, using keywords such as: abnormal/ unmonitored effluent release, etc.
LIST OF ACRONYMS ALARA As Low As Reasonably Achievable ARM Area Radiation Monitor CAM Continuous Air Monitor CAP Corrective Action Program CR Condition Report DAW Dry Active Waste ED Electronic Dosimeter HEPA High Efficiency Particulate HP Health Physics HRA High Radiation Area ISFSI Independent Spent Fuel Storage Installation LHRA Locked High Radiation Area NCR Nuclear Condition Report NIST National Institute of Standards and Technology 6
NSTS National Source Tracking System NVLAP National Voluntary Laboratory Accreditation Program ODCM Offsite Dose Calculation Manual OOS Out-of-Service PCE Personnel Contamination Event PCM Personnel Contamination Monitor PM Personnel Monitor radworker Radiation Worker RAM Radioactive Material RCA Radiological Controlled Area RWP Radiation Work Permit SAM Small Article Monitor SCBA Self-Contained Breathing Apparatus SFP Spent Fuel Pool SSCs Systems, Structures, and Components TLD Thermoluminescent Dosimeter U1 / U2 Unit 1 / Unit 2 VHRA Very High Radiation Area WBC Whole Body Counter 7