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Category:Evacuation Time Estimate/Report (ETE)
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error 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-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 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-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) 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-23-0716, 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-23-0704, 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-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums 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-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 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-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report 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-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 2024-01-30
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Charles R. Pierce Southern Nuclear Regulatory AHairs Director Operating Company. Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205 9927872 Fax 2059927601 SOUIHERN ' \
March 28, 2013 COMPANY Docket Nos.: 50-348 50-321 50-424 NL-13-0634 50-364 50-366 50-425 U. S. Nuclear Regulatory Commission AnN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 & 2 Edwin I. Hatch Nuclear Plant - Units 1 & 2 Vogtle Electric Generating Plant - Units 1 & 2 Evacuation Time Estimate Update
References:
- 1. Southern Nuclear Operating Company letter NL-12-2329 to the NRC, Joseph M. Farley Nuclear Plant - Units 1 and 2, Evacuation Time Estimate Update, dated December 7,2012
- 2. Southern Nuclear Operating Company letter NL-12-2330 to the NRC, Edwin I. Hatch Nuclear Plant - Units 1 and 2, Evacuation Time Estimate Update, dated December 7, 2012
- 3. Southern Nuclear Operating Company letter NL-12-2331 to the NRC, Vogt/e Electric Generating Plant - Units 1 and 2, Evacuation Time Estimate Update, dated December 7, 2012 Ladies and Gentlemen:
During the Nuclear Regulatory Commission (NRC) review of the above referenced Southern Nuclear Operating Company submittals, it was identified that additional information was needed regarding Section 8, "Sensitivity Study on Population Change," for each submittal. In addition, it was identified that the statement in the Section 8 Sensitivity Study regarding the NRC's review and approval of the 2012 Evacuation Time Estimate (ETE) study should be removed .
Enclosures 1, 2, and 3 provide an updated copy of Section 8, Sensitivity Study on Population Change, for Joseph M. Farley Nuclear Plant - Units 1 and 2 (FNP),
Edwin I. Hatch Nuclear Plan - Units 1 and 2 (HNP), and Vogtle Electric Generating Plant - Units 1 and 2 (VEGP), respectively.
U. Nuclear Regulatory Commission NL-1 ,rv,u...,..,.
Page 2 This letter contains no NRC commitments. If you have any questions, contact Ken McElroy (205) 992-7369.
Respectfully submitted,
- t. t{ lZ.
C. R. Pierce Regulatory Affairs Director CRP/RMJ/lac
- 1. FNP Section 8, Sensitivity Study on Population Change Revised HNP Section 8, Sensitivity Study on Population Change Revised Section 8, Sensitivity Study on Population Change cc: Southern Nuclear Operating Company Mr. Kuczynski, Chairman, President & CEO Mr. D. Bast, Executive Vice President & Chief Nuclear Officer Mr. T. Lynch, Vice President - Farley Mr. D. Madison, Vice President - Hatch Mr. E. Tynan, Vice President - Vogtle Mr. L. Ivey, Vice President - Regulatory Affairs Mrs. Reister, Emergency Preparedness Manager RType: CFA04.054; CHA02.004; CVC7000 Mr. V. M. McCree, Regional Administrator Mr. E. Martin, NRR Project Manager - Hatch, Vogtle Mr. D. Morris, Resident Inspector - Hatch Mr. L. M. Cain, Senior Resident Inspector - Vogtle Ms. E. A. Brown, NRR Project Manager - Farley Mr. K~ Niebaum, . . . or"......
Mr. J. R. Sowa, Senior Resident Inspector - Farley Georgia Emergency Management Agency Mr. S. Clark, Radiological Emergency Planning Program Director South Carolina Office of the Adiutant General Emergency Management Mr. N. Nienhius, Fixed Nuclear Facility Coordinator
Joseph M. Nuclear Plant - Units 1 & 2 Edwin I. Hatch Nuclear Plant - Units 1 & 2 Vogtle Generating Plant - 1&2 Estimate Enclosure 1 Revised FNP Section 8, Sensitivity Study on Population Change
EVACUATION TIME ESTIMATES FOR THE JOSEPH M. FARLEY NUCLEAR PLANT 8.0 SENSITIVITY STUDY ON POPULATION CHANGE ETEs vary with factors such as population, roadway networks and vehicle occupancy rates. In response to new federal regulations, IEM conducted a population sensitivity analysis for FNP to address the uncertainty in population data by estimating the anticipated impact of a population change on ETEs. This sensitivity analysis wiJi provide a basis for decisions on future ETE update thresholds.
IEM increased the residential population (for both EPZ and shadow evacuees) to determine the population value that will cause ETE values to increase by 25 percent or 30 minutes, whichever is less for the scenario with the longest ETE. This scenario is evacuating the entire EPZ during the weekday under adverse weather conditions. The base ETE for this scenario is 200 minutes, and hence the threshold for triggering an ETE update is a 30 minute increase in the ETE. IEM found that an increase of 30 minutes occurs with a permanent resident population increase of 161 % or 6,409 people within the EPZ (along with the increase of shadow evacuees with the same percentage).
IEM 2012 Page 69
Joseph M. Farley Nuclear - Units 1 & 2 I. Hatch Nuclear Plant Units 1 & 2 Vogtle Electric Generating - Units 1 & 2 Evacuation Time Update Enclosure 2 HNP Section 8, Sensitivity Study on Population Change
EVACUATION TIME ESTIMATES FOR THE EDWIN I. HATCH NUCLEAR PLANT 8.0 SENSITIVITY STUDY ON POPULATION CHANGE ETEs vary with factors such as population, roadway networks and vehicle occupancy rates. In response to new federal regulations, IEM conducted a population sensitivity analysis for HNP to address the uncertainty in population data by estimating the anticipated impact of a population change on ETEs. This sensitivity analysis will provide a basis for decisions on future ETE update thresholds.
IEM increased the residential population (for both EPZ and shadow evacuees) to determine the population value that will cause ETE values to increase by 25 percent or 30 minutes, whichever is less for the scenario with the longest ETE. This scenario is evacuating the entire EPZ during the weekend under adverse weather conditions. The base ETE for this scenario is 235 minutes, and hence the threshold for triggering an ETE update is a 30 minute increase in the ETE. IEM found that an increase of 30 minutes occurs with a permanent resident population increase of 40% or 3,444 people within the EPZ (along with the increase of shadow evacuees with the same percentage).
IEM 2012 Page 65
Joseph M. Nuclear Plant - Units 1 & 2 Edwin I. Hatch Nuclear Plant - 1&2 Vogtle Generating Plant - 1&2 Evacuation Time Estimate Update Enclosure 3 nt;!vls.t;!u VEGP Section 8, Sensitivity Study on Population Change
EVACUATION TIME ESTIMATES FOR THE VOGTLE ELECTRIC GENERATING PLANT
!s.o SENSITIVITY STU DY ON POPULATION CHANGE ETEs vary with the factors such as population, roadway networks and vehicle occupancy rates. In response to new federal regulations, IEM conducted a population sensitivity analysis for VEGP to address the uncertainly in population data by estimating the anticipated impact of a population change on ETEs . This sensitivity analysis will provide a basis for decisions on future ETE update thresholds.
IEM increased the residential population (for both EPZ and shadow evacuees) to determine the population value that will cause ETE values to increase by 25 percent or 30 minutes, whichever is less for the scenario with the longest ETE. This scenario is evacuating the entire EPZ during the weekend under adverse weather conditions. The base ETE for this scenario is 205 minutes, and hence the threshold for triggering an ETE update is a 30 minute increase in the ETE. !EM found that an increase of 30 minutes occurs with a permanent resident population increase of 278 % or 8,671 people within the EPZ (along with the increase of shadow evacuees wjth the same percentage) .
IEM 2012 Page 61