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| | issue date = 05/05/2010 | | | issue date = 05/05/2010 |
| | title = Generic Ltr. 2004-02 Supplemental Response (TAC MC4684 and MC4685) | | | title = Generic Ltr. 2004-02 Supplemental Response (TAC MC4684 and MC4685) |
| | author name = Martin R E | | | author name = Martin R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Ajluni M | | | addressee name = Ajluni M |
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| | page count = 3 | | | page count = 3 |
| | project = TAC:MC4684, TAC:MC4685 | | | project = TAC:MC4684, TAC:MC4685 |
| | stage = Supplement | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 5,2010 Mr. Mark J. Ajluni Manager, Nuclear Licensing Southern Nuclear Operating Company, Inc 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1AND 2 -GENERIC LEDER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4684 AND MC4685) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 5,2010 Mr. Mark J. Ajluni Manager, Nuclear Licensing Southern Nuclear Operating Company, Inc 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 |
| | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1AND 2 - GENERIC LEDER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4684 AND MC4685) |
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| ==Dear Mr. Ajluni:== | | ==Dear Mr. Ajluni:== |
| By letters dated February 28, April 29, and December 17, 2008; July 27,2009; and March 30, 2010; Southern Nuclear Operating Company (SNC) submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2. We have reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the U.S. Nuclear Regulatory Commission's (NRC's) "Content Guide for Generic Letter 2004-02 Supplemental Responses" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML07311 0389). The review process also included a separate review of your submittal informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate. | | |
| The NRC staff has no further questions for FNP at this time regarding completion of corrective actions for GL 2004-02. This conclusion is based on the NRC staffs evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated March 9, 2009. As you may be aware, we have not yet issued a final safety evaluation (SE) on WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." The NRC staff has reviewed the GL 2004-02 submittals for FNP and determined that SNC currently intends to rely on the conclusions reached in WCAP-16793-NP. | | By letters dated February 28, April 29, and December 17, 2008; July 27,2009; and March 30, 2010; Southern Nuclear Operating Company (SNC) submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2. We have reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the U.S. Nuclear Regulatory Commission's (NRC's) "Content Guide for Generic Letter 2004-02 Supplemental Responses" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073110389). The review process also included a separate review of your submittal informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate. |
| Assuming disposition ofWCAP-16793-NP results in NRC staff issuance of an SE, the NRC intends to send a letter requesting that SNC confirm whether it still intends to rely on the conclusions reached in WCAP-16793-NP for FNP. In addition, the letter will likely request a response within 60 days describing, (1) the means SNC used to determine the amount of debris that bypasses the emergency core cooling system strainer, (2) the fiber loading expected per fuel assembly for the cold-leg and hot-leg break scenarios based on information available as of the date of the letter, (3) the available head loss margins with bases for the cold-leg and hot-leg break scenarios using the WCAP-16793 acceptance criteria, and (4) SNC's planned actions for FI\lP should it exceed an acceptance criterion. | | The NRC staff has no further questions for FNP at this time regarding completion of corrective actions for GL 2004-02. This conclusion is based on the NRC staffs evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated March 9, 2009. |
| The I\IRC staff will M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We not requesting any information from SNC on this subject at this If you have any further questions on this matter, please contact me at Sincerely, Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We not requesting any information from SNC on this subject at this If you have any further questions on this matter, please contact me at Sincerely, IRA! Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ DISTRIBUTION PUBLIC LPLlI-1 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrLASRohrer Resource RidsRgn2MailCenter Resource RidsNrrPMFarleyResource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsOgcRp Resource RidsNrrDssSsib Resource ADAMS Accession No ML 101230051 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/SSIB/BC NRR/LPL2-1/BC NAME RMartin SRohrer MScott GKulesa (JStang for) DATE 05/04/10 05/03/10 05/04/10 05/05/10 OFFICIAL RECORD COpy}} | | As you may be aware, we have not yet issued a final safety evaluation (SE) on WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." The NRC staff has reviewed the GL 2004-02 submittals for FNP and determined that SNC currently intends to rely on the conclusions reached in WCAP-16793-NP. Assuming disposition ofWCAP-16793-NP results in NRC staff issuance of an SE, the NRC intends to send a letter requesting that SNC confirm whether it still intends to rely on the conclusions reached in WCAP-16793-NP for FNP. In addition, the letter will likely request a response within 60 days describing, (1) the means SNC used to determine the amount of debris that bypasses the emergency core cooling system strainer, (2) the fiber loading expected per fuel assembly for the cold-leg and hot-leg break scenarios based on information available as of the date of the letter, (3) the available head loss margins with bases for the cold-leg and hot-leg break scenarios using the WCAP-16793 acceptance criteria, and (4) |
| | SNC's planned actions for FI\lP should it exceed an acceptance criterion. The I\IRC staff will |
| | |
| | M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from SNC on this subject at this time. |
| | If you have any further questions on this matter, please contact me at 301-415-1493. |
| | Sincerely, i |
| | /Uf)J(~~v Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ |
| | |
| | M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from SNC on this subject at this time. |
| | If you have any further questions on this matter, please contact me at 301-415-1493. |
| | Sincerely, IRA! |
| | Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ DISTRIBUTION PUBLIC LPLlI-1 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrLASRohrer Resource RidsRgn2MailCenter Resource RidsNrrPMFarleyResource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsOgcRp Resource RidsNrrDssSsib Resource ADAMS Accession No ML101230051 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/SSIB/BC NRR/LPL2-1/BC NAME RMartin SRohrer MScott GKulesa (JStang for) |
| | DATE 05/04/10 05/03/10 05/04/10 05/05/10 OFFICIAL RECORD COpy}} |
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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)
MONTHYEARML24227A0512024-08-14014 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 ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 2024-08-14
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 5,2010 Mr. Mark J. Ajluni Manager, Nuclear Licensing Southern Nuclear Operating Company, Inc 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1AND 2 - GENERIC LEDER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4684 AND MC4685)
Dear Mr. Ajluni:
By letters dated February 28, April 29, and December 17, 2008; July 27,2009; and March 30, 2010; Southern Nuclear Operating Company (SNC) submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2. We have reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the U.S. Nuclear Regulatory Commission's (NRC's) "Content Guide for Generic Letter 2004-02 Supplemental Responses" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073110389). The review process also included a separate review of your submittal informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate.
The NRC staff has no further questions for FNP at this time regarding completion of corrective actions for GL 2004-02. This conclusion is based on the NRC staffs evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated March 9, 2009.
As you may be aware, we have not yet issued a final safety evaluation (SE) on WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." The NRC staff has reviewed the GL 2004-02 submittals for FNP and determined that SNC currently intends to rely on the conclusions reached in WCAP-16793-NP. Assuming disposition ofWCAP-16793-NP results in NRC staff issuance of an SE, the NRC intends to send a letter requesting that SNC confirm whether it still intends to rely on the conclusions reached in WCAP-16793-NP for FNP. In addition, the letter will likely request a response within 60 days describing, (1) the means SNC used to determine the amount of debris that bypasses the emergency core cooling system strainer, (2) the fiber loading expected per fuel assembly for the cold-leg and hot-leg break scenarios based on information available as of the date of the letter, (3) the available head loss margins with bases for the cold-leg and hot-leg break scenarios using the WCAP-16793 acceptance criteria, and (4)
SNC's planned actions for FI\lP should it exceed an acceptance criterion. The I\IRC staff will
M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from SNC on this subject at this time.
If you have any further questions on this matter, please contact me at 301-415-1493.
Sincerely, i
/Uf)J(~~v Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ
M. Ajluni -2 notify you of the expected timeline for any needed actions at the time the SE is issued, or will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from SNC on this subject at this time.
If you have any further questions on this matter, please contact me at 301-415-1493.
Sincerely, IRA!
Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc: Distribution via ListServ DISTRIBUTION PUBLIC LPLlI-1 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrLASRohrer Resource RidsRgn2MailCenter Resource RidsNrrPMFarleyResource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsOgcRp Resource RidsNrrDssSsib Resource ADAMS Accession No ML101230051 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/SSIB/BC NRR/LPL2-1/BC NAME RMartin SRohrer MScott GKulesa (JStang for)
DATE 05/04/10 05/03/10 05/04/10 05/05/10 OFFICIAL RECORD COpy