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| | number = ML11312A186 | | | number = ML11312A186 |
| | issue date = 11/21/2011 | | | issue date = 11/21/2011 |
| | title = Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies (TAC Nos. ME6430 and ME6431) | | | title = Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies |
| | author name = Jaffe D H | | | author name = Jaffe D |
| | 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 = Jaffe D H, NRR/DORL/LPL2-1, 415-1439 | | | contact person = Jaffe D, NRR/DORL/LPL2-1, 415-1439 |
| | case reference number = TAC ME6430, TAC ME6431, BL-11-001 | | | case reference number = TAC ME6430, TAC ME6431, BL-11-001 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:ME6430, TAC:ME6431 | | | project = TAC:ME6430, TAC:ME6431 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 21, 2011 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 (FARLEY 1 AND 2) REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING 60-DAY RESPONSE TO BULLETIN 2011-01, "MITIGATING STRATEGIES" (TAC NOS. ME6430 AND ME6431) Dear Mr. Ajluni: On May 11,2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 111250360), to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The purpose of the bulletin was to obtain a comprehensive verification that licensees' mitigating strategies to maintain or restore core cooling, spent fuel cooling, and containment following a large explosion or fire were compliant with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(hh)(2). The bulletin requested information on licensee 10 CFR 50.54(hh)(2) mitigating strategies in light of the recent events at Japan's Fukushima Daiichi facility to determine if (1) additional assessment of program implementation is needed, (2) the current inspection program should be enhanced, or (3) further regulatory action is warranted. The bulletin required two sets of responses pursuant to the provisions of 10 CFR 50.54(f). The first responses were due 30 days after issuance of the bulletin (June 10, 2011). By letter dated June 10,2011 (ADAMS Accession No. ML 11165A009), you provided a response to the first set of questions for Farley 1 and 2. The second responses were due 60 days after issuance of the bulletin (July 11, 2011). By letter dated July 7, 2011 (ADAMS Accession No. ML 11196A093), you responded to this second set of questions. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 21, 2011 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| M. Ajluni The NRC staff has reviewed the submitted information and determined that it needs additional information regarding your 60-day response to the bulletin. Please respond to the enclosed request for additional information within 30 days of the date of this letter. If you have any questions regarding this letter, please feel free to contact David H. Jaffe at (301) 415-1439. Sincerely, " '\'Jti',Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Enclosure: RAI cc w/encl: Distribution via Listserv JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND REQUEST FOR ADDITIONAL INFORMATION NUCLEAR REGULATORY COMMISSION (NRC) BULLETIN "MITIGATING DOCKET NOS. 50-348 AND Describe in detail how you ensure that a vehicle is available to move the B.5.b portable pump and other B.5.b equipment to the appropriate place when needed. The bulletin requested that each licensee describe in detail the controls for ensuring equipment needed to execute the mitigating strategies will be available when needed. A vehicle is typically needed to implement the strategies since the portable pump and other equipment is stored away from target areas. The NRC staff could not determine if you performed activities to ensure that a tow vehicle would be available when needed. Enclosure M. Ajluni -The NRC staff has reviewed the submitted information and determined that it needs additional information regarding your 60-day response to the bulletin. Please respond to the enclosed request for additional information within 30 days of the date of this letter. If you have any questions regarding this letter, please feel free to contact David H. Jaffe at (301) 415-1439. Sincerely, IRA! David H. Jaffe, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Enclosure: RAI cc w/encl: Distribution via Listserv DISTRI BUTION: PUBLIC LPL 2-1 RlF BPurnell, NRR EBowman SRosenberg, NRR RidsNrrLA MO'Brien Resource RidsNrrPMFarley Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsOgcRp Resource RidsAcrsAcnw _MailCTR Resource RidsRgn 2MailCenter Resource ADAMS Accession No ML 11312A 186 OFFICE DORULPL2-1/PM DORULPL2-1/LA DPR/PCGB/PM NAME DHJaffe MO'Brien BPurneli DATE 11117/11 11116/11 11/17/11 OFFICE DPR/PCGB/BC DORULPL2-1/BC DORULPL2-1/PM NAME SRosenberg GKulesa DHJaffe DATE 11/17/11 11/21/11 11/21/11 OFFICIAL RECORD COPY | | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| }} | | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FARLEY 1 AND 2) |
| | REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING 60-DAY RESPONSE TO BULLETIN 2011-01, "MITIGATING STRATEGIES" (TAC NOS. |
| | ME6430 AND ME6431) |
| | |
| | ==Dear Mr. Ajluni:== |
| | |
| | On May 11,2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS) |
| | Accession No. ML111250360), to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The purpose of the bulletin was to obtain a comprehensive verification that licensees' mitigating strategies to maintain or restore core cooling, spent fuel cooling, and containment following a large explosion or fire were compliant with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(hh)(2). The bulletin requested information on licensee 10 CFR 50.54(hh)(2) mitigating strategies in light of the recent events at Japan's Fukushima Daiichi facility to determine if (1) additional assessment of program implementation is needed, (2) the current inspection program should be enhanced, or (3) further regulatory action is warranted. |
| | The bulletin required two sets of responses pursuant to the provisions of 10 CFR 50.54(f). The first responses were due 30 days after issuance of the bulletin (June 10, 2011). By letter dated June 10,2011 (ADAMS Accession No. ML11165A009), you provided a response to the first set of questions for Farley 1 and 2. The second responses were due 60 days after issuance of the bulletin (July 11, 2011). By letter dated July 7, 2011 (ADAMS Accession No. ML11196A093), |
| | you responded to this second set of questions. |
| | |
| | M. Ajluni -2 The NRC staff has reviewed the submitted information and determined that it needs additional information regarding your 60-day response to the bulletin. Please respond to the enclosed request for additional information within 30 days of the date of this letter. |
| | If you have any questions regarding this letter, please feel free to contact David H. Jaffe at (301) 415-1439. |
| | Sincerely, |
| | 'Jti' D~~I '*~ak:: |
| | \ ' |
| | Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 |
| | |
| | ==Enclosure:== |
| | |
| | RAI cc w/encl: Distribution via Listserv |
| | |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING NUCLEAR REGULATORY COMMISSION (NRC) BULLETIN 2011-01, "MITIGATING STRATEGIES" DOCKET NOS. 50-348 AND 50-364 |
| | : 1. Describe in detail how you ensure that a vehicle is available to move the B.5.b portable pump and other B.5.b equipment to the appropriate place when needed. |
| | The bulletin requested that each licensee describe in detail the controls for ensuring equipment needed to execute the mitigating strategies will be available when needed. A vehicle is typically needed to implement the strategies since the portable pump and other equipment is stored away from target areas. The NRC staff could not determine if you performed activities to ensure that a tow vehicle would be available when needed. |
| | Enclosure |
| | |
| | ML11312A186 OFFICE DORULPL2-1/PM DORULPL2-1/LA DPR/PCGB/PM NAME DHJaffe MO'Brien BPurneli DATE 11117/11 11116/11 11/17/11 OFFICE DPR/PCGB/BC DORULPL2-1/BC DORULPL2-1/PM NAME SRosenberg GKulesa DHJaffe DATE 11/17/11 11/21/11 11/21/11}} |
Letter Sequence RAI |
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MONTHYEARNL-11-0984, Response to NRC Bulletin 2011-01, Mitigating Strategies2011-06-10010 June 2011 Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request NL-11-1148, Day Response to NRC Bulletin 2011-01, Mitigating Strategies2011-07-0707 July 2011 Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request ML11312A1862011-11-21021 November 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: RAI NL-11-2389, Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, Mitigating Strategies2011-12-15015 December 2011 Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: Response to RAI ML12125A2412012-05-25025 May 2012 Closeout of Bulletin 2011-01, Mitigating Strategies (TAC Nos. ME6430 and ME6431) Project stage: Other 2011-06-10
[Table View] |
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Category:Letter
MONTHYEARNL-24-0364, Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R342024-10-31031 October 2024 Notification of Deferral of Baffle Former Bolt Inspections from Farley 1R33 to 1R34 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0396, Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing2024-10-25025 October 2024 Response to Request for Additional Information Related to Relief Request to Defer Charging Pump and Mini-Flow Isolation Valve Inservice Testing NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves2024-10-18018 October 2024 Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves NL-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-24-0340, 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 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 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 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 ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time 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 05000348/LER-2024-002-01, 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) 05000348/LER-2024-001, 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 05000364/LER-2024-002, 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 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 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 2024-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24290A1572024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley and Vogtle 1 and 2 - Alternative Request for Pressurizer Welds (L-2024-LLR-0047) ML24271A0052024-09-26026 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 2024-09-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 21, 2011 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 (FARLEY 1 AND 2)
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING 60-DAY RESPONSE TO BULLETIN 2011-01, "MITIGATING STRATEGIES" (TAC NOS.
ME6430 AND ME6431)
Dear Mr. Ajluni:
On May 11,2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML111250360), to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The purpose of the bulletin was to obtain a comprehensive verification that licensees' mitigating strategies to maintain or restore core cooling, spent fuel cooling, and containment following a large explosion or fire were compliant with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54(hh)(2). The bulletin requested information on licensee 10 CFR 50.54(hh)(2) mitigating strategies in light of the recent events at Japan's Fukushima Daiichi facility to determine if (1) additional assessment of program implementation is needed, (2) the current inspection program should be enhanced, or (3) further regulatory action is warranted.
The bulletin required two sets of responses pursuant to the provisions of 10 CFR 50.54(f). The first responses were due 30 days after issuance of the bulletin (June 10, 2011). By letter dated June 10,2011 (ADAMS Accession No. ML11165A009), you provided a response to the first set of questions for Farley 1 and 2. The second responses were due 60 days after issuance of the bulletin (July 11, 2011). By letter dated July 7, 2011 (ADAMS Accession No. ML11196A093),
you responded to this second set of questions.
M. Ajluni -2 The NRC staff has reviewed the submitted information and determined that it needs additional information regarding your 60-day response to the bulletin. Please respond to the enclosed request for additional information within 30 days of the date of this letter.
If you have any questions regarding this letter, please feel free to contact David H. Jaffe at (301) 415-1439.
Sincerely,
'Jti' D~~I '*~ak::
\ '
Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
RAI cc w/encl: Distribution via Listserv
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING NUCLEAR REGULATORY COMMISSION (NRC) BULLETIN 2011-01, "MITIGATING STRATEGIES" DOCKET NOS. 50-348 AND 50-364
- 1. Describe in detail how you ensure that a vehicle is available to move the B.5.b portable pump and other B.5.b equipment to the appropriate place when needed.
The bulletin requested that each licensee describe in detail the controls for ensuring equipment needed to execute the mitigating strategies will be available when needed. A vehicle is typically needed to implement the strategies since the portable pump and other equipment is stored away from target areas. The NRC staff could not determine if you performed activities to ensure that a tow vehicle would be available when needed.
Enclosure
ML11312A186 OFFICE DORULPL2-1/PM DORULPL2-1/LA DPR/PCGB/PM NAME DHJaffe MO'Brien BPurneli DATE 11117/11 11116/11 11/17/11 OFFICE DPR/PCGB/BC DORULPL2-1/BC DORULPL2-1/PM NAME SRosenberg GKulesa DHJaffe DATE 11/17/11 11/21/11 11/21/11