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MONTHYEARNL-12-1893, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2012-09-25025 September 2012 License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request ML12345A3982012-12-12012 December 2012 Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742)(NL-12-1893) Project stage: Acceptance Review NL-12-2566, Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2012-12-20020 December 2012 Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML13022A1582013-01-24024 January 2013 Acceptance Review Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (N-1-2-1893) Project stage: Acceptance Review ML13050A2862013-02-22022 February 2013 3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology Project stage: RAI ML13067A2692013-03-11011 March 2013 03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Meeting ML13176A0932013-07-0808 July 2013 Request for Additional Information Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (NL-12-1893) Project stage: RAI ML14038A0192013-09-16016 September 2013 Joseph M. Farley, Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generati Project stage: Request NL-13-2039, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-10-30030 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-13-2269, Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-11-12012 November 2013 Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML14066A0472014-03-0707 March 2014 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742 Project stage: Draft RAI ML14073A0532014-03-28028 March 2014 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML14114A5502014-04-23023 April 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0733, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-05-23023 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0927, Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 32014-07-0303 July 2014 Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 3 Project stage: Response to RAI ML14176A0702014-07-11011 July 2014 Request for Additional Information Project stage: RAI NL-14-1106, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants2014-08-11011 August 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants Project stage: Response to RAI NL-14-1273, Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants2014-08-29029 August 2014 Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants Project stage: Response to RAI NL-14-1937, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2015-01-16016 January 2015 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML15023A0522015-01-23023 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Request ML15043A4592015-02-24024 February 2015 Summary of Site Audit to Support the Review of a License Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2, to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis Project stage: Approval ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) Project stage: Approval 2014-03-28
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Category:Letter type:NL
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 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 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 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) 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-24-0201, 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-24-0238, 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 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 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 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 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. 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 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, To Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 To Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 2024-09-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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-24-0259, 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 ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time 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 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-24-0234, 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-24-0238, 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-24-0064, 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-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions 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-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-21-0989, License Amendment Request to Relocate Augmented Piping Inspection Program Details2021-12-22022 December 2021 License Amendment Request to Relocate Augmented Piping Inspection Program Details NL-21-0925, Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2021-12-22022 December 2021 Adoption of TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves NL-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure2021-12-13013 December 2021 License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure NL-21-0930, Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-10-21021 October 2021 Joseph F. Farley Nuclear Plant, Units 1 & 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements NL-21-0658, Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections2021-09-17017 September 2021 Joseph Farley, Units 1 and 2, Vogtle, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for for Steam Generator Tube Inspections NL-21-0613, Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, .2021-06-30030 June 2021 Supplement to License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, . NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications2021-06-22022 June 2021 License Amendment Request to Remove Table of Contents from Technical Specifications NL-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System2021-06-0909 June 2021 Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System NL-21-0065, License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls2021-03-25025 March 2021 License Amendment Request to Revise Technical Specification 5.7, High Radiation Area, Administrative Controls NL-20-0949, License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 22020-10-30030 October 2020 License Amendment Request to Revise, Technical Specifications to Adopt TSTF-541, Revision 2 ML20224A4642020-08-11011 August 2020 Southern Nuclear Operating Co, Inc - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML20192A1402020-06-30030 June 2020 Southern Nuclear Operating Co., Inc. - License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2020-05-29029 May 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues NL-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors2019-12-12012 December 2019 License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors NL-19-0963, Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process2019-12-11011 December 2019 Removal of the Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications Using Consolidated Line Item Improvement Process NL-19-1063, Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition2019-12-10010 December 2019 Units 1 and 2 and Vogtle Electric Generating Plant, Units 1 and 2 - Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition NL-19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-07-15015 July 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes2019-06-27027 June 2019 Risk Informed Technical Specification Information Only Bases Changes NL-18-0668, Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2018-12-14014 December 2018 Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material NL-18-1189, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-4712018-11-29029 November 2018 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-471 ML18226A0942018-08-0909 August 2018 Edwin I. Hatch, Units 1 and 2; and Vogtle, Units 1 and 2 - License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum On-shift Staff Tables NL-18-0039, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ...2018-07-27027 July 2018 License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk Managed Technical Specifications (Rmts) ... NL-18-0733, Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information2018-06-0707 June 2018 Supplement to License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow and Response to Request for Additional Information ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures NL-17-0190, Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process2017-12-21021 December 2017 Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process NL-17-0611, Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow2017-12-21021 December 2017 Units 1 and 2, License Amendment Request for Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow NL-17-1088, Submittal of License Amendment Request, Relocation of the Emergency Operations Facility2017-08-30030 August 2017 Submittal of License Amendment Request, Relocation of the Emergency Operations Facility NL-16-2384, Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.12017-03-22022 March 2017 Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.1 ML15329A0322017-01-23023 January 2017 Issuance of Amendment Related to Renewed Facility Operating License Condition 2.C.(23) Required Completion Date ML16340A0052016-12-0101 December 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Rev 4, Clarify Use and Application Rules. NL-16-1026, Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2016-11-21021 November 2016 Units 1 & 2, Vogtle Electric Generating Plant- Units 1 & 2 - Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements 2024-09-04
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Sensitive Information. Withhold from public Mark J. Ajiluni, P.E. Southern Nuclear disclosure per 10 CFR 2.390. Decontrolled Nuclear Licensing Director Operating Company, Inc. upon removal of Attachments C, D, G, S, 40 Inverness Center Parkway and W from Enclosure 1.
Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 SOUTHERN Nm COMPANY September 25, 2012 Docket Nos.: 50-348 NL-1 2-1893 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
Ladies and Gentlemen:
In accordance with 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to amend Renewed Facility Operating License No. NPF-2 for Joseph M. Farley Nuclear Plant (FNP) Unit 1 and FNP Unit 2 Renewed Facility Operating License No. NPF-8. This License Amendment Request (LAR) requests the Nuclear Regulatory Commission (NRC) review and approval for adoption of a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a), 10 CFR 50.48(c), and the guidance in Regulatory Guide (RG) 1.205, Revision 1. to this letter contains the FNP NFPA 805 LAR (Transition Report).
SNC considers Attachments C, D, G, S, and W to Enclosure 1 to be sensitive information and requests that it be withheld from public disclosure pursuant to 10 CFR 2.390. A redacted version is provided as Enclosure 2. In an effort to clarify the FNP approach to NRC concerns with previous LAR submittals that may have FNP applicability, Enclosure 3 provides a table to address each of the "Generic RAIs" identified by the Nuclear Energy Institute (NEI) NFPA 805 Task Force.
This letter contains no NRC commitments. As part of the activities associated with the transition to NFPA 805, FNP shall implement the necessary modifications to complete the transition to full compliance with 10 CFR 50.48(c).
A list of modifications and a schedule for completion is provided in LAR (Transition Report) Attachment S. Implementation of new NFPA 805 fire protection program shall include procedure changes, process updates, and training to affected plant personnel. This will be completed 180 days after NRC approval.
Sensitive Information. Withhold from public U.S. Nuclear Regulatory Commission disclosure per 10 CFR 2.390. Decontrolled NL-1 2-1893 upon removal of Attachments C, D,G, S, Page 2 and W from Enclosure 1.
If you have any questions, please contact Mr. Ken McElroy at (205) 992-7369.
Mr. Ajluni states he is Nuclear Licensing Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
S toand subsc* dbefore me this day of Ljp 2012.
Notary Pdblic My commission expires: (( Z- Zo 13 Respectfully submitted, M. J. Ajluni Nuclear Licensing Director MJAGAL/lac
Enclosures:
- 1. NFPA 805 LAR Transition Report
- 2. NFPA 805 LAR Transition Report (Redacted Version)
- 3. Generic RAIs cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
Enclosure 3 Generic RAIs
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 1 Monitoring Program (ML113210461 - FAQ 59 will 11/18/11 Meeting Added additional information added to FNP will create a NFPA Slide 11) - Closure of FAQ 59 is address this topic. ML113210461 Section 4.6 in LAR Template (Rev. 1 N). 805 Monitoring Program necessary and clarification on use of ML113340218 Mirrors RAI responses for Callaway and similar to the maintenance rule ML120750108 DAEC Maintenqance Rule for HSS Fire Protection FAQ 59, Rev. 5 sent to NRC 02/10/12. Features and Systems. It Technical agreement reached on 2/16/12. will be documented in the NFPA 805 Monitoring Task Force considers this issue closed. Program Engineering NRC agreed this issue closed 6/28/12. Evaluation to be developed during Implementation.
2 Seismic standpipes/Hose Stations Additional dialogue 11/18/11 Meeting The exception to Section 3.6.4 is not FNP LAR Attachment A, (ML113210461 -Slide 12) - The NRC with the NRC is ML113210461 endorsed. The NRC is asking licensees Section 3.6.4 includes the wants additional information on the ability needed on this ML113340218 without seismic hose stations to discuss resolution deemed to fight fires following an earthquake. topic. how they would fight a fire in the event of acceptable by the NRC.
a seismic event. This seems to be in conflict with Section III. Comment Resolution on Proposed Rule in the Federal Register.
Discussed at 4/26/12 FAQ meeting. This topic will be eliminated as a generic RAI and plant specific RAIs will be "pulled back" based on NRC discussion with legal staff. ML121370055 Discussed at the 5/24/12 FAQ meeting.
LAR template note will suggest that licensees' (operating plants and plants with construction permits issued prior to July 1, 1976 with non-seismic standpipes and hose stations previously approved in accordance with Appendix A to BTP APCSB 9.5-1) utilize "complies via previous approval" for this Section of NPFA 805.
Task Force considers this issue closed.
NRC agreed this issue closed 6/28/12.
1
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 3 Total CDF/LERF (ML113210461-Slide 13) Guidance on this 11/18/11 Meeting Added "Note to LAR Developer" in Aft. W. FNP LAR Attachment W,
-NRC indicated that the last sentence on topic is already in ML113210461 No technical change made to LAR Table W-1 provides the Slide 13 was incorrect and the CDF and the LAR template ML113340218 Template (Rev. 1L). summary of total plant risk LERF values should be E-06 and E-07, (Rev. 1k), Section (total CDF and LERF) respectively. W.2 Task Force considers this issue closed, including other external NRC agreed this issue closed 6/28/12. events reported.
4 FSAR (ML113210461-Slide 14) - Industry Make FSAR 11/18/11 Meeting This topic is not being handled FNP LAR Section 5.2 expressed concern that the NRC had content an ML113210461 consistently between the transitioning includes FSAR discussion.
changed their mind on this topic and is attachment in NEI ML113340218 plants. Is there a need to treat this as a Reference to FAQ 62 is requesting information that previously had 04-02, Rev. 3, generic topic. made in the LAR with been identified as not necessary. NRC rather than part of respect to FSAR content acknowledged the change in direction the LAR. NRC Change made to LAR Template (Rev. 1 L) and format.
and referred to guidance in RG 1.174 and desires general Section 5.4 (Section 5.4 Transition SRP 19.2 as some of the rationale for information, not an Schedule renumbered to Section 5.5).
desiring information on FSAR content FSAR markup or Added "Note to LAR Developer" detailed information. FAQ 12-0062 received technical agreement at FAQ meeting 5/24/12.
Task Force considers this issue closed.
NRC agreed this issue closed 6/28/12.
5 Defense-in-Depth/Safety Margin LAR Template 11/18/11 Meeting Change made to LAR Template (Rev. 1 L) There is still uncertainly on (ML113210461-Slide 15)- The NRC Section 4.5.2.2 to ML113210461 Section 4.5.2.2. the level of detail the NRC expressed concern that guidance on the include additional ML113340218 is expecting. FNP LAR process simply referred to NEI 04-02, information from Additional discussion with the NRC is Section 4.5.2.2 is rather than describing the process in the FAQ 54 to address needed to determine closure method. enhanced with discussion LAR. They indicated that they do not this concern NRC to review LAR template discussion. of defense in depth.
want detailed information by Fire Area. Additional details are provided in the Fire Risk Evaluation (FRE) report, consistent with LAR template Rev. 1N.
2
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 6 Fire PRA Quality (ML113210461 -Slide The NFPA 805 TF 11/18/11 Meeting Added "Note to LAR Developer" to Tables FNP LAR Section U and V
- 16) - Inconsistent use of terms was the will work with the ML113210461 U-1 and V-1 that discusses closure of writers confirmed main concern (focused scope peer Fire PRA TF to ML113340218 F&Os, treatment of suggestion F&Os, and consistent terminology and review, gap assessment, etc.) clarify terminology adequate documentation of F&O content of these sections and update the resolution. meet anticipated NRC LAR template, as expectations.
necessary (Aft. U, Need to add the NEI guidance that V). provides guidance for these terms. NEI to look at terms for Fire PRA quality.
7 Post-Transition Change Process Guidance about 11/18/11 Meeting Added "Note to LAR Developer" in Section FNP LAR Section 4.7.2 is (ML113210461-Slide 17) -The NRC this is provided in ML113210461 4.7.2 of LAR Template (Rev. 1L) and consistent with the Generic wants to know more on site specific the LAR template ML113340218 referred to an example (utility response Template and other implementation. The industry expressed (Rev. 1k) Section dated 9/27/10 and 8/13/2009). industry submittals.
concern about being able to provide a lot 4.7.2. FAQ 61 Industry questions the of specifics with the LAR submittal. The (under Task Force considers this issue closed, generic nature of this RAI NRC indicated that some level of detail on development) will NRC to review LAR template discussion. as it showed up only at one which site specific processes and help address this utility and the industry procedures would be modified would topic. responses are very similar.
need to be provided in the LAR FAQ 61 is under NRC review.
8 Non-Power Operations (ML113210461- The TF will update 11/18/11 Meeting Added "Note to LAR Developer" in FNP LAR Attachment D Slide 18) - The NRC wants more detailed the LAR template ML113210461 Attachment D of LAR Template (Rev. 1 L). includes the statement "No information in the LAR on pre-fire actions (Section 4.3.2, Aft. ML113340218 pre-fire actions or recovery to prevent spurious operation (e.g., D) to address this Task Force considers this issue closed, actions were credited in removal of power to component) and topic, rather than NRC agreed this issue closed 6/28/12. developing the pinch point recovery actions. trying to revise FAQ tables."
40.
9 B-2 Table (ML113210461-Slide 19) - The The TF will review 11/18/11 Meeting No change to LAR Template (Rev. 1L) FNP LAR Attachment 2 -
concern was that B-2 table statements and see if ML113210461 Table B-2 (when should reference how the post-transition additional guidance ML113340218 Task Force to monitor to see if additional completed) will be program meets the guidance, and not is needed in LAR guidance is warranted. reviewed to ensure no reference Appendix R or superseded template (Section reference to Appendix R is documents. 4.2.1, Aft. B). made.
3
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 10 NEI 00-01 Rev. 2 (ML113210461-Slide The NRC would like 11/18/11 Meeting Added additional discussion and "Note to FNP LAR Section 4.2.1.1
- 20) - Although FAQ 39 endorsed Rev. 1 a gap analysis of ML113210461 LAR Developer" to LAR Template (Rev. includes discussion on the of NEI 00-01 Chapter 3 in the B-2 table, Rev. 2 vs. Rev. 1 of ML113340218 1L) Section 4.2.1.1. additional review the NRC referenced Rev. 2 of NEI 00-01 NEI 00-01 and a performed to NEI 00-01 in RG 1.205 Rev. 1. The NRC would like discussion of the Task Force developed a list of the Revision 2.
a gap analysis of Rev. 2 vs. Rev. 1 of NEI gap analysis and 'substantive change topics' 00-01 and a discussion of the gap results in the LAR analysis and results in the LAR submittal. submittal (Section Task Force considers this issue closed.
4.2.1, Att. B).. NRC agreed this issue closed 6/28/12.
11 Safe and Stable (ML113210461-Slide 21) Guidance on this 11/18/11 Meeting No change to LAR Template (Rev. 1 L) FNP LAR Section 4.2.1.2
- The NRC would like a justification topic is already ML113210461 does not include a defined (qualitative risk analysis) if a defined time available in FAQ 54 ML113340218 Additional reviews indicate that the NRC time period.
period is specified. and in the LAR may desire a qualitative risk analysis even template. (Section if a defined time period is not specified. FNP does not include a 4.2.1.2) statement on qualitative NEI will clarify in template that qualitative risk analysis. It is not clear risk analysis should be provided whether exactly what the NRC or not a defined time period is provided in expectations are. FNP is safe and stable definition, consistent with other recent submittals. This item is not deemed to be a LIC 109 risk, but has potential for an RAI.
12 Complies with Clarification It was believed that 11/18/11 Meeting No change made to LAR Template (Rev. FNP LAR Attachment A (ML113210461-Slide 22) - This concern sufficient guidance ML113210461 1 L). uses the 'Complies with was referencing an incorrect compliance exists on this topic. ML113340218 Clarification" compliance statement. Task Force to monitor to see if additional statement twice. Each guidance is warranted. case is used appropriately.
13 Redaction of Security Related Information NEI-NRC to work 11/18/11 Meeting Not characterized as "Generic RAI" at LAR redaction will be done (ML113210461 -Slide 27) on approach ML113210461 11/18/11 meeting. No change made to by FNP licensing at their ML113340218 LAR Template (Rev. 1 L). discretion.
Discussed 6/27 - 6/28/12. NEI to revise template to remove redactions of entire statement and reference guidance from NRC (with decision on specifics ultimately left to individual plant processes).
4
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 14 Treatment of FPRA Unreviewed Analysis Industry needs 11/18/11 Meeting Not characterized as "Generic RAI" at FNP Fire PRA has not Methods (UAMs) (ML113210461 -Slide clear understanding ML113210461 11/18/11 meeting. used any UAM; however, 61). of how UAMs are ML113340218 SNC has used methods treated and closed No change made to LAR Template (Rev. which are not explicitly out. 1 L). defined in NUREG/CR-6850. These methods are Additional discussion with the NRC is discussed in item 27.
needed to determine closure method.
15 NRC now asking for 10 CFR Two utilities New item discussed at 3/22/12 TF The FNP LAR did not 50.48(c)(2)(vii) submittal for use of EPRI meeting. address this generic RAI process for surveillance optimization topic. This specific topic is uses. (two utilities) Need additional discussion with staff to still developing and under determine path for closure. Industry discussion with the NRC.
working on generic response to this topic. Both pilot plants did not use this approach and received SE's. This item is not deemed to be a LIC 109 risk, but has the high potential for an RAI 5
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 16 FPRA - Sensitivity study on CPT factor 2. New item discussed at 3/22/12 TF FNP Fire PRA does a RAI's for several meeting. sensitivity analysis on all It was recently stated at the industry fire utilities and hot short probabilities by forum that the Phenomena Identification "generic" Need additional discussion with staff to multiplying them by a factor and Ranking Table Panel being RAIs (#9) determine path for closure, of 2. The results from this conducted for the circuit failure tests from sensitivity study are the DESIREEFIRE and CAROL-FIRE 6/28/12 - Additional discussion needed discussed in Att V of LAR.
tests may be eliminating the credit for on how to treat this Fire PRA topic (not Control Power Transformers (CPTs) necessarily as a LAR template item). NEI (about a factor 2 reduction) currently to work on how to treat Fire PRA topics allowed by Tables 10-1 and 10-3 of likely to get extensive reviews/RAIs.
NUREG/CR-6850, Vol. 2, as being invalid when estimating circuit failure probabilities. Provide a sensitivity analysis that removes this CPT credit from the PRA and provide new results that show the impact of this potential change on CDF, LERF, ACDF, and ALERF. If the sensitivity analysis indicates that the change in risk acceptance guidelines would be exceeded after eliminating CPT credit, please justify not meeting the guidelines.
17 Please describe how your evaluation "generic" This is addressed by SRs within the PRA The increase in total heat includes the possible increase in heart RAIs (#1) Standard. release rate due to (sic) release rate caused by the spread of intervening combustibles is a fire from the ignition source to other 6/28/12 -Additional discussion needed considered in the Farley combustibles. Please summarize how on how to treat this Fire PRA topic (not Fire PRA.
suppression is included in your necessarily as a LAR template item). NEI evaluation. to work on how to treat Fire PRA topics likely to get extensive reviews/RAIs.
6
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 18 Transient fires should at a minimum be "generic" This is addressed by SRs within the PRA A transient fire is placed in locations within the plant PAUs RAIs (#2) Standard. postulated in any location where CCDPs are highest for that PAU, that it is plausible.
i.e., at "pinch points." Pinch points include 6/28/12 - Additional discussion needed Plausible in this context, locations of redundant trains or the vicinity on how to treat this Fire PRA topic (not based on plant specific of other potentially risk-relevant necessarily as a LAR template item). NEI physical features.
equipment, including the cabling to work on how to treat Fire PRA topics associated with each. Transient fires likely to get extensive reviews/RAIs. FNP scenario report should be placed at all appropriate describes the transient locations in a PAU where they can scenario identification threaten pinch points. Hot work should be process.
assumed to occur in locations where hot work is a possibility, even if improbable (but not impossible), keeping in mind the same philosophy.
19 Discuss the calculation of the frequencies "generic" This is addressed by SRs within the PRA A discussion is provided in of transient and hot work fires. RAIs (#3, 4) Standard. the Farley Plant Characterize your use of the influence Partitioning and Ignition factors for maintenance, occupancy, and 6/28/12 - Additional discussion needed Frequency Development storage, noting if the rating "3" is the most on how to treat this Fire PRA topic (not report includes a common, as it is intended to be necessarily as a LAR template item). NEI discussion for influence representative of the "typical" weight for to work on how to treat Fire PRA topics factors used other than "3".
each influence factor. likely to get extensive reviews/RAIs.
The assignments are FAQ 12-64 addresses this topic. based on insights from a plant review panel.
7
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 20 Section 10 of NUREG/CR-6850 "generic" This is addressed by SRs within the PRA This sensitivity study is Supplement 1 states that a sensitivity RAIs (#7) Standard. presented in Att V of the analysis should be performed when using LAR. Because SNC plans the fire ignition frequencies in the 6/28/12 - Additional discussion needed to reestablish baseline and Supplement instead of the fire ignition on how to treat this Fire PRA topic (not delta risk estimates by frequencies provided in Table 6-1 of necessarily as a LAR template item). NEI replacing 2012 industry NUREG/CR-6850. Provide the sensitivity to work on how to treat Fire PRA topics consensus electrical analysis of the impact on using the likely to get extensive reviews/RAIs. cabinet model with Supplement 1 frequencies instead of the NURG/CR-6950 model, no Table 6-1 frequencies on CDF, LERF, additional work is ACDF, and ALERF for all of those bins performed to justify the that are characterized by an alpha that is results of the sensitivity less than or equal to one. If the sensitivity study. Rather, the ignition analysis indicates that the change in risk frequency study will be acceptance guidelines would be revised concurrently with exceeded using the values in Table 6-1, changes in baseline and please justify not meeting the guidelines, delta risk estimates.
21 Please describe how CDF and LERF are "generic" This is addressed by SRs within the PRA Scenarios have been estimated in main control room (MCR) RAIs (#8) Standard. defined that cause MCR abandonment scenarios. Do any fires Abandonment. A range of outside of the MCR cause MCR 6/28/12 - Additional discussion needed screening values are used.
abandonment because of loss of control on how to treat this Fire PRA topic (not and/or loss of control room habitability? necessarily as a LAR template item). NEI The FRE report and the Are "screening" values for post MCR to work on how to treat Fire PRA topics FNP Scenario report abandonment used (e.g., conditional core likely to get extensive reviews/RAIs. include additional damage probability of failure to information for MCR successfully switch control to the Primary scenarios.
Control Station and achieve safe 3 shutdown of 0.1) or have detailed human error analyses been completed for this activity. Please justify any screening value used.
8
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 22 Attachment W of the LAR provides the "generic" This is a candidate for revision to LAR The methodology used for
..CDF and ..LERF for the variances from RAIs (#10) template. performing fire risk the deterministic requirements (VFDRs) evaluations is discussed in for each of the fire areas, but the LAR Added section to Attachment W. Att W of the LAR.
does not describe either generically or specifically how ..CDF and ..LERF were 6/28/12 - Additional discussion needed All of the methods utilized calculated. Describe the method(s) used on how to treat this Fire PRA topic (not in the development of FNP to determine the changes in risk reported necessarily as a LAR template item). NEI Fire PRA have been peer in the Tables in Appendix W. The to work on how to treat Fire PRA topics reviewed.
description should include: likely to get extensive reviews/RAIs. NEI to look at existing guidance. No new operator actions a) A summary of PRA model additions or are credited in the change modifications needed to determine the in risk estimates.
reported changes in risk. If any of these model additions used data or methods not included in the fire PRA Peer Review please describe the additions.
b) Identification of new operator actions (not including post MCR abandonment which are addressed elsewhere) that have been credited in the change in risk estimates. If such actions are credited, how is instrument failure addressed in the HRA.
23 Did the peer reviews for both the internal "generic" Added the following note to LAR Both the FNP Fire and events and fire PRAs consider the RAIs (#11) Developer in Attachment U: Internal Events PRAs have clarifications and qualifications from undergone a RG 1.200, Regulatory Guide (RG) 1.200, Revision 2, Provide a general discussion of the Revision 2, Peer Review.
"An Approach for Determining the standards against which the Internal Technical Adequacy of Probabilistic Risk Events PRA has been reviewed. Ensure Assessment Results for Risk- Informed that RG 1.200 Revision 2 has been Activities," March 2009 (ADAMS considered.
Accession No. ML090410014) to the ASME/AMS PRA Standard? If not, 6/28/12 - NRC questioned RG 1.200 Rev.
provide a self-assessment of the PRA 2 for fire and asked to ensure guidance in model for the RG 1.200 clarifications and LAR template addressed fire.
qualifications and indicate how any identified gaps were dispositioned.
9
Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 24 Identify if any variance from deterministic "generic" See item 22 Not applicable. FNP does requirement (VFDRs) in the LAR involved RAIs (#12) not have VFDRs related to performance-based evaluations of embedded or wrapped wrapped or embedded cables. If cables.
applicable, describe how wrapped or embedded cables were modeled in the Fire PRA including assumptions and insights on how the PRA modeling of these cables contributes to the VFDR delta risk evaluations.
25 Identify any plant modification "generc" Added a note to LAR developer in An implementation item is (implementation item) in Attachment S of RAIs (#13) Attachment S. identified in Table S-3 of the LAR that have not been completed the LAR. This but which have been credited directly or The task force considers this issue closed, implementation item will indirectly in the change-in-risk estimates Task Force considers this issue closed, adjust the FNP Fire PRA to provided in Attachment W. When the NRC to review LAR template discussion. reflect the as built plants affects of a plant modification has been after modifications have included in the PRA before the been implemented.
modification has been completed, the models and values used in the PRA are Should the condition arise necessarily estimates based on current such that the as-built plans. The as-built facility after the change-in-risk exceed modification is completed may be different estimates reported in the than the plans. Please add an LAR, Corrective action implementation item that, upon would take place.
completion of all PRA credited implementation items, verifies the validity of the reported change-in-risk. This item should include your plan of action should the as-built change-in-risk exceed the estimates reported in the LAR.
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Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 26 Please identify any changes made to the "generic" This is a candidate for revision to LAR There have been no internal events or fire PRA since the last RAIs (#14) template. changes to the internal full scope peer review of each of these events or Fire PRA model PRA models that are consistent with the 6/28/12 - NEI to review for possible that would be considered a definition of a "PRA upgrade" in updates to LAR template. "PRA upgrade" since the ASME/ANS-RA-Sa-2009, as endorsed by last full scope Peer Regulatory Guide 1.200. Also, please Review.
address the following:
i) If any changes are characterized as a PRA upgrade, please identify if a focused scope peer review was performed for these changes consistent with the guidance in ASME/ANS-RA-Sa-2009, as endorsed by Regulatory Guide 1.200, and describe any findings from that focused-scope peer review and the resolution of these findings for this application.
ii) ii) If a focused-scope peer review has not been performed for changes characterized as a PRA upgrade, please describe what actions will be implemented to address this review deficiency.
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Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 27 During the 5/24/12 public meeting the The staff has This is addressed by SRs within the PRA FNP Fire PRA has used NRC asked that the licensee identify noticed that this Standard. one alternate analysis deviations from NUREG/CR 6850 has been treated method (Panel Severity methods including those that involve inconsistently in the Need additional discussion with staff to Factor) to NUREG/CR-justifications. submittals. determine path for closure (i.e., the 6850 which is discussed in correct amount of information to be the FNP LAR Attachment included in the LAR versus supporting V. This discussion documentation. includes the results from a sensitivity study. Although the sensitivity study yields results estimated delta CDF/LERF values around the acceptance criteria defined in RG 1.174, SNC intends to follow direction from the NRC staff to replace the 2012 industry consensus electrical cabinet model with the model prescribed by NUREG/CR-6850.
28 Clarification between IEEE-383 Flame 6/27/12 Public This is not necessarily a LAR template The FNP Scenario report Spread Rating and damage threshold Meeting (Slide 8) item, but a topic that should be discusses the types of understood by licensees in preparation of cables installed in the plant the LAR. and their damage threshold. This is discussed in terms of the damage threshold of thermoplastic and thermoset cables.
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Generic RAIs - Southern FNP Comparison No. Topic-Generic Issue Actions / Ref. Status/Comment FNP Disposition Disposition 29 NFPA 805 Quality Section 2.7.3 - NRC 6/27/12 Public Candidate for LAR template revision. FNP LAR Section 4.7.3 is concerns about future commitment to Meeting (Slide 9) consistent with the Generic meet 2.7.3 (specific concerns over post Template and other LAR transition qualifications) submittal with respect to the discussion of Quality requirements.
This item is new and not officially on the NRC Generic RAI list at this time. No action taken to change LAR approach as NRC expectations are not entirely clear at this point.
This item is still developing, therefore an RAI may be expected.
30 Clarification needed on risk and delta risk 6/27/12 Public Need additional discussion with NRC on Modifications were criteria related to credit for modifications, Meeting PRA this topic. Candidate for LAR template included in the analysis to additional risk of recovery actions Slides (Slide 5) revision after clarification obtained and decrease the cumulative agreed upon. total risk and the total delta risk to ensure that the acceptance criteria defined by RG 1.174 is met. The additional risk of recovery actions are included in Aft W.
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