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Category:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature ML21179A2352021-06-25025 June 2021 PSEG Salem Generating Station - Incidental Take Report Atlantic Sturgeon 6/24/2021 ML21078A0002021-03-25025 March 2021 Review of the Spring 2020 Steam Generator Tube Inspection Report LR-N21-0004, U.S Additional Protocol for Salem, Unit 12021-01-31031 January 2021 U.S Additional Protocol for Salem, Unit 1 LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report ML20274A0762020-09-25025 September 2020 PSEG to NRC, Biological and Engineering Evaluation of Alternatives in Connection with Reinitation of Endangered Species Act Section 7 Consultation LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N19-0103, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20192019-11-26026 November 2019 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2019 LR-N19-0010, U.S. Additional Protocol for Salem Unit 1 2018 Report2019-01-31031 January 2019 U.S. Additional Protocol for Salem Unit 1 2018 Report ML19029B0172019-01-29029 January 2019 Containment Building, Salem Nuclear Generating Station, Structural Analysis & Design LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 ML18337A3262018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for April 11, 2018 (1 of 2) ML18337A3252018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for March 28, 2018 ML18337A3242018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for February 6, 2018 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0076, Focused Evaluation of External Flooding2017-06-30030 June 2017 Focused Evaluation of External Flooding LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0051, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2017-02-16016 February 2017 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-30030 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16280A5232016-08-31031 August 2016 Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0026, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2016-02-26026 February 2016 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N15-0218, Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-21021 October 2015 Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report LR-N15-0207, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report2015-10-0707 October 2015 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. ML15119A1612015-04-17017 April 2015 Report of Impingement of Atlantic Sturgeon LR-N14-0268, Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days2014-12-24024 December 2014 Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days 2023-09-06
[Table view] Category:Technical
MONTHYEARML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N21-0004, U.S Additional Protocol for Salem, Unit 12021-01-31031 January 2021 U.S Additional Protocol for Salem, Unit 1 LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report ML20274A0762020-09-25025 September 2020 PSEG to NRC, Biological and Engineering Evaluation of Alternatives in Connection with Reinitation of Endangered Species Act Section 7 Consultation LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N19-0103, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20192019-11-26026 November 2019 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2019 ML19029B0172019-01-29029 January 2019 Containment Building, Salem Nuclear Generating Station, Structural Analysis & Design LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 ML18337A3242018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for February 6, 2018 ML18337A3252018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for March 28, 2018 ML18337A3262018-01-30030 January 2018 Sturgeon Incidental Take Report and Data Collection Form for April 11, 2018 (1 of 2) LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16280A5232016-08-31031 August 2016 Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. ML15030A3012014-09-22022 September 2014 Table 08, Unit 2 Seismic Gap Drain Tritium Analytical Results ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2762014-09-22022 September 2014 Figure 11, Station Wind Summary - Q1 2014 ML15030A2752014-09-22022 September 2014 Figure 10, Precipitation Measurements ML15030A2512014-09-22022 September 2014 Figure 9, Salem Generating Station Hydrogeologic Cross Section E-E' ML15030A2502014-09-22022 September 2014 Figure 8,Salem Generating Station Hydrogeologic Cross Section D-D' ML15030A2492014-09-22022 September 2014 Figure 7, Salem Generating Station Hydrogeologic Cross Section C-C' ML15030A2482014-09-22022 September 2014 Figure 6, Salem Generating Station Hydrogeologic Cross Section B-B' ML15030A2472014-09-22022 September 2014 Figure 5, Salem Generating Station Hydrogeologic Cross Section A-A' ML15030A2462014-09-22022 September 2014 Figure 4, Station Shallow Groundwater Elevation Contours - February 2014 ML15030A2452014-09-22022 September 2014 Figure 3, Salem Generating Station Layout Map ML15030A2792014-09-22022 September 2014 Figure 13, Tritium Isoconcentration Map - March 2014 ML15030A2802014-09-22022 September 2014 Figure 14, Historic Tritium Recovered Through Well Field Operation ML15030A2442014-09-22022 September 2014 Figure 2, Station Layout Map ML15030A2432014-09-22022 September 2014 Figure 1, Site Location Map ML15030A2422014-09-22022 September 2014 Appendix a, Mass Flux Calculations ML15030A2812014-09-22022 September 2014 Figure 15, Salem Unit 1 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2822014-09-22022 September 2014 Figure 16, Salem Unit 2 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2832014-09-22022 September 2014 Table 01, Well Construction Details ML15030A2842014-09-22022 September 2014 Table 02, Sample Collection Schedule - First & Second Quarter 2014 ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2962014-09-22022 September 2014 Table 05, Groundwater Analytical Results (1.22.2003 Through 3.31.2014) ML15030A2982014-09-22022 September 2014 Table 06A, Groundwater Tritium Analytical Results for Well AC ML15030A2992014-09-22022 September 2014 Table 06B, Groundwater Analytical Results for Well AC ML15030A3002014-09-22022 September 2014 Table 07, Unit 1 Seismic Gap Drain Tritium Analytical Results 2023-09-06
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APPENDIX H Evacuation Regions H EVACUATION REGIONS This appendix presents the evacuation percentages for each Evacuation Region (Table H-i) and maps of all Evacuation Regions. The percentages presented in Table H-1 are based on the methodology discussed in assumption 5 of Section 2.2 and shown in Figure 2-1.Note the baseline ETE study assumes 20 percent of households will not comply with the shelter advisory, as per Section 2.5.2 of NUREG/CR-7002.
Salem-Hope Creek NGS Evacuation Time Estimate H-1 KLD Engineering, P.C.Rev. 0 Table H-1. Percent of ERPA Population Evacuating for Each Region-Basic Regions Region Description R01 2-Mile Ring 20% 20% 20% 20% 20% 20% 20% 20% 20%R02 5-Mile Ring 20% 20% 20% 20% 20% 20%R03 Full EPZ Evacuate S-Mile Radius and Downwind to the EPZ Boundary Region Wind Direction ERPA Rein From:2 3 4 6 7 A B C R04 N, NNE, NE 20% 20% 20% 20% 20% 20%ROS ENE, E, ESE 20% 20% 20% 20% 20% 20%R06 SE20 20 20 20 20 202%R0720% 20% 20%R08 2 20% 20% 20%R09 SSW, SW20 2%2%R10 WSW202%2%1111 W, WNW 2%2% 0 R12 NW20 20 2%R13 NNW20 20 2%2%Staged Evacuation
-S-Mile Radius Evacuates, then Evacuate Downwind to the EPZ Boundary Region Wind Direction ERPA From: 1 2 3 4 S 6 7 8 R14 None R15 N, NNE, NE R16 ENE, E, ESE 20% 20% 20% 20% 20% 20%R17 SE20 20 20 20 20 2%R18 SSE R19 SShler-n-lc R20 SSW, SW20 2%R21 WSW202%R22 W, WNW20 2%2%R23 NW20 20 20 2%R24 NNW20 20 20 2%2%Delaware Only R25 ERPA A 2% 2%2%2%2%2%2%_0 0 0 R26 ERPA B 2% 2%2%2%2%2%2%2%2!
0 0 R27 ERPA C 20 20 20 20 20 20 20 20 i0 2%2%R28 Delaware 2% 2%2%2%2%2%2%2%::
Key Salem-Hope Creek NGS Evacuation Time Estimate H-2 KLD Engineering, P.C.Rev. 0 Figure H-1. Region RO0 H-3 KLD Engineering, P.C.Salem-Hope Creek NGS Evacuation Time Estimate ID H-3 KLD Engineering, P.C.Rev. 0 0 Figure H-2. Region R02 Salem-Hope Creek NGS Evacuation Time Estimate H-4 KLD Engineering, P.C.Rev. 0 Figure H-3. Region R03 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-5 KLD Engineering, P.C.Rev. 0 0 Figure H-4. Region R04 Salem-Hope Creek NGS Evacuation Time Estimate H-6 KLD Engineering, P.C.Rev. 0 FigUre H-5. Region R05 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-7 KLD Engineering, P.C.Rev. 0 0 0 Figure H-6. Region R06 H-8 KLD Engineering, P.C.Salem-Hope Creek NGS Evacuation Time Estimate H-8 KLD Engineering, P.C.Rev. 0 Figure H-7. Region R07 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-9 KLD Engineering, P.C.Rev. 0 0 Figure H-8. Region ROB Salem-Hope Creek NGS Evacuation Time Estimate H-10 KLD Engineering, P.C.Rev. 0 Figure H-9. Region R09 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-11 KLD Engineering, P.C.Rev. 0 0 Figure H-10. Region RIO Salem-Hope Creek NGS Evacuation Time Estimate H-12 KLD Engineering, P.C.Rev. 0 Figure H-11. Region R11 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-13 KLD Engineering, P.C.Rev. 0 0 Figure H-12. Region R12 Salem-Hope Creek NGS Evacuation Time Estimate H-14 KLD Engineering, P.C.Rev. 0 Figure H-13. Region R13 Salem-Hope Creek NGS Evacuation Time Estimate 40 H-15 KLD Engineering, P.C.Rev. 0 is Figuire H-14. Region R14 Salem-Hope Creek NGS Evacuation Time Estimate H-16 KLD Engineering, P.C.Rev. 0 Figure H-15. Region R15 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-17 KLD Engineering, P.C.Rev. 0 0 Figure H-16. Region R16 Salem-Hope Creek NGS Evacuation Time Estimate H-18 KLD Engineering, P.C.Rev. 0 Figure H-17. Region R17 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-19 KLD Engineering, P.C.Rev. 0 0 Figure H-18. Region RIS Salem-Hope Creek NGS Evacuation Time Estimate H-20 KLD Engineering, P.C.Rev. 0 Figure H-19. Region R19 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-21 KLD Engineering, P.C.Rev. 0 0 Figure H-20. Region R20 Salem-Hope Creek NGS Evacuation Time Estimate H-22 KLD Engineering, P.C.Rev. 0 Figure H-21. Region R21 Salem-Hope Creek NGS Evacuation Time Estimate 40 H-23 KLD Engineering, P.C.Rev. 0 0 Figure H-22. Region R22 H-24 KLD Engineering, P.C.Salem-Hope Creek NGS Evacuation Time Estimate H-24 KLD Engineering, P.C.Rev. 0 Figure H-23. Region R23 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-25 KLD Engineering, P.C.Rev. 0 0 Figure H-24. Region R24 H-26 KLD Engineering, P.C.Salem-Hope Creek NGS Evacuation Time Estimate H-26 KLD Engineering, P.C.Rev. 0 Figure H-25. Region R25 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-27 KLD Engineering, P.C.Rev. 0 0 Figure H-26. Region R26 Salem-Hope Creek NGS Evacuation Time Estimate H-28 KLD Engineering, P.C.Rev. 0 Figure H-27. Region R27 Salem-Hope Creek NGS Evacuation Time Estimate 0 H-29 KLD Engineering, P.C.Rev. 0 is Figure H-28. Region R28 Salem-Hope Creek NGS Evacuation Time Estimate H-30 KLD Engineering, P.C.Rev. 0 APPENDIX J Representative Inputs to and Outputs from the DYNEV II System J. REPRESENTATIVE INPUTS TO AND OUTPUTS FROM THE DYNEV II SYSTEM This appendix presents data input to and output from the DYNEV II System. Table J-1 provides the volume and queues for the ten highest volume signalized intersections in the study area.Refer to Table K-2 and the figures in Appendix K for a map showing the geographic location of each intersection.
Table J-2 provides source (vehicle loading) and destination information for several roadway segments (links) in the analysis network. Refer to Table K-1 and the figures in Appendix K for a map showing the geographic location of each link.Table J-3 provides network-wide statistics (average travel time, average speed and number of vehicles) for an evacuation of the entire EPZ (Region R03) for each scenario.
As expected, Scenarios 8 and 11, which are snow scenarios, exhibit the slowest average speed and longest average travel times.Table J-4 provides statistics (average speed and travel time) for the major evacuation routes -State Route 49 in New Jersey, and State Route I and US Route 13 in Delaware -for an evacuation of the entire EPZ (Region R03) under Scenario 1 conditions.
Table J-5 provides the number of vehicles discharged and the cumulative percent of total vehicles discharged for each link exiting the analysis network, for an evacuation of the entire EPZ (Region R03) under Scenario I conditions.
Refer to Table K-1 and the figures in Appendix K for a map showing the geographic location of each link.Figure J-1 through Figure J-14 plot the trip generation time versus the ETE for each of the 14 Scenarios considered.
The distance between the trip generation and ETE curves is the travel time. Plots of trip generation versus ETE are indicative of the level of traffic congestion during evacuation.
For low population density sites, the curves are close together, indicating short travel times and minimal traffic congestion.
For higher population density sites, the curves are farther apart indicating longer travel times and the presence of traffic congestion.
As seen in Figure J-1 through Figure J-14, the curves are spatially separated as a result of the traffic congestion in the EPZ, which was discussed in detail in Section 7.3.Salem-Hope Creek NGS J-1 KLD Engineering, P.C.Evacuation Time Estimate Rev. 0 Table J-1. Characteristics of the Ten Highest Volume Signalized Intersections lUiL U U 125 US-40 and SR 896 TCP 126 6,180 0 618 1,203 0 1153 431 0 TOTAL 7,814 163 5,042 0 165 1,435 0 164 US-13 and SR 273 Actuated 945 110 0 944 900 0 TOTAL 7,487 81 4,845 0 156 1,478 0 77 US-13 and Hamburg Actuated 965 621 0 Road 82 94 0 TOTAL 7,038 159 3,980 0 631 995 0 160 US-13 and US-40 Actuated 161 1,464 0 TOTAL 6,439 158 4,462 0 159 US-13 and Llangollen Actuated 160 1,465 0 Boulevard 950 488 0 TOTAL 6,415 -117 0 0 121 3,695 0 SR 896 and Old123,90 120 Bali ore Actuated 921 0 0 Baltimore Pike 922 2,708 0 TOTAL 6,403 77 1,479 0 865 1,444 204 81 US-13 and SR 71 Actuated 952 3,392 49 TOTAL 6,315 Salem-Hope Creek NGS Evacuation Time Estimate J-2 KLD Engineering, P.C.Rev. 0 Appoac Toa Max Turn0 IIntreto (U -Voum Queue 127 0 0 128 SR 896 and Porter Rd Actuated 129 6,053 0 917 127 0 1028 0 0 TOTAL 6,180 738 4,299 67 24 0 0 23 US-13 and Duck 23 Rd Actuated 911 1,864 0 Creek Rd 991 14 0 TOTAL 6,177 -30 3,856 0 US-13 and Black 26 1,894 0 Diamond Rd 1117 172 0 TOTAL 5,922 -Salem-Hope Creek NGS Evacuation Time Estimate J-3 KLD Engineering, P.C.Rev. 0 Table J-2. Sample Simulation Model Input 690 73 E 8275 1,348 775 237 NE 8272 1,125 8102 3,810 935 5 W 8014 4,500 8111 4,500 1221 260 SW 8010 3,810 8014 4,500 8224 9,000 1726 137 W 8222 6,750 8111 4,500 629 6 NE 8272 1,125 842 6 NE 8272 1,125 1171 61 S 8705 1,572 8755 1,698 8818 5,715 1454 77 N 8249 4,500 8246 4,500 1628 18 W 8102 3,810 Salem-Hope Creek NGS Evacuation Time Estimate J-4 KLD Engineering, P.C.Rev. 0 Table J-3. Selected Model Outputs for the Evacuation of the Entire EPZ (Region R03)Scenario 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Network-Wide Average Travel Time (Min/Veh-Mi) 1.8 2.0 1.6 1.8 1.6 1.8 2.0 2.1 1.6 1.8 1.8 1.6 2.0 2.0 Network-Wide Average 34.3 30.6 36.6 32.8 36.5 34.1 30.0 29.0 37.7 32.6 33.3 36.5 30.6 30.0 Speed (mph)Total Vehicles Exitin Network 56,746 57,137 51,179 51,545 43,551 57,045 57,410 57,614 49,799 50,166 50,235 43,551 58,163 56,751 Exiting Network Salem-Hope Creek NGS Evacuation Time Estimate J-5 KLD Engineering, P.C.Rev. 0 Table J-4. Average Speed (mph) and Travel Time (min) for Major Evacuation Routes (Region R03, Scenario 1)Elapsed Tie(hus 2 3 4--S *~S a-Travel~SR 49 SB (NJ) 11.5 36.5 19.0 51.2 13.5 151.2 113.5 152.3 113.2 SR 49 NB (NJ) 11.5 18.7 37.0 46.6 14.9 46.9 14.8 48.0 14.4 SR 1 SB (DE) 19.7 64.5 18.3 65.0 18.2 64.9 18.2 64.9 18.2 SR 1 NB (DE) 19.7 65.0 18.2 65.0 18.2 65.0 18.2 65.0 18.2 US-13 SB (DE) 18.6 49.2 22.6 56.1 19.8 57.7 19.3 57.9 19.2 US-13 SB (DE) 18.5 46.8 23.7 53.5 20.8 53.3 20.9 53.5 20.8 Salem-Hope Creek NGS Evacuation Time Estimate J-6 KLD Engineering, P.C.Rev. 0 Table J-5. Simulation Model Outputs at Network Exit Links for Region R03, Scenario 1~Cumulative Vehicles Discharged by the Indicated Time Cumulative Percent of Vehicles Discharged by the Indicated Time 243 1,299 1,627 1,713 1,730 17.°.L.. I ) 5.. 3. 1 1.1 24 3,380 7,221 7,979 8,184 8,211 28.8 19.5 16.0 14.8 14.5 222 2,118 4,428 5,601 6,100 6,186 18.0 11.9 11.2 11.0 10.9 0 400 470 471 471 241 0.0 1.1 0.9 0.9 0.8 244 1,009 3,830 5,842 6,704 6,835 8.6 10.3 11.7 12.1 12.1 0 0 0 0 0 253 253 0.0 0.0 0.0 0.0 0.0 630 2,747 3,851 4,363 4,446 388 5.4 7.4 7.7 7.9 7.8 759 2,301 3,294 3,836 3,935 6.5 6.2 6.6 6.9 6.9 107 610 866 952 966 406 0.9 1.6 1.7 1.7 1.7 6 66 100 109 110 424 0.1 0.2 0.2 0.2 0.2 67 577 837 926 941 481 0.6 1.6 1.7 1.7 1.7 66 553 837 932 942 488 0.6 1.5 1.7 1.7 1.7 22 275 411 448 452 509 0.2 0.7 0.8 0.8 0.8 758 1,764 2,764 3,764 4,394 624 6.5 4.8 5.5 6.8 7.8 1 16 26 29 30 635 0.0 0.0 0.1 0.1 0.1 28 145 213 236 239 638 0.2 0.4 0.4 0.4 0.4 0 5 8 11 12 651 0.0 0.0 0.0 0.0 0.0 Salem-Hope Creek NGS Evacuation Time Estimate J-7 KLD Engineering, P.C.Rev. 0 EP 1 1 Cumlaiv VeilsLicageiythnniatdTm 4 108 166 179 181 738 0.0 0.3 0.3 0.3 0.3 0 12 20 22 22 759 0.0 0.0 0.0 0.0 0.0 31 136 193 210 214 770 0.3 0.4 0.4 0.4 0.4 0 1 1 1 1 855 0.0 0.0 0.0 0.0 0.0 82 177 214 224 224 881 0.7 0.5 0.4 0.4 0.4 33 380 531 557 561 996 0.3 1.0 1.1 1.0 1.0 39 433 656 714 724 1180 0.3 1.2 1.3 1.3 1.3 3 27 41 45 46 1469 0.0 0.1 0.1 0.1 0.1 1 1 1 1 1 1530 0.0 0.0 0.0 0.0 0.0 4 28 44 50 50-1539 0.0 0.1 0.1 0.1 0.1 232 517 816 1,041 1,059 1711 2.0 1.4 1.6 1.9 1.9 3 28 43 47 47 1754 0.0 0.1 0.1 0.1 0.1 9 46 65 71 72 1819 0.1 0.1 0.1 0.1 0.1 71 1,104 1,230 1,231 1,231 1823 0.6 3.0 2.5 2.2 2.2 1 1 1 1 1 1844 0.0 0.0 0.0 0.0 0.0 845 2,028 2,883 3,056 3,073 1851 7.2 5.5 5.8 5.5 5.4 65 1,062 1,531 1,654 1,680 1858 0.6 2.9 3.1 3.0 3.0 27 34 77 109 122 1870______0.2 0.1 0.2 0.2 0.2 Salem-Hope Creek NGS Evacuation Time Estimate J-8 KLD Engineering, P.C.Rev. 0 Cumultive Ehilapes Discared by(heo Idiatdsim Cumlaiv Pecn of Veice Dicare byte5dctdTm 943 3,963 5,570 6,094 6,180 1890 943 6,094 5,570+ + I 8.0 10.7 11.2 11.0 10.9 92 525 763 867 889 1891t 0.8 1.4 1.5 1.6 1.6 71 263 399 443 448 1897 1 0.6 0.7 0.8 0.8 0.8 Salem-Hope Creek NGS Evacuation Time Estimate J-9 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Summer, Midweek, Midday, Good (Scenario 1)-Trip Generation IETE VI 4-0 0 U'100%80%60%40%20%0%0 30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-1. ETE and Trip Generation:
Summer, Midweek, Midday, Good Weather (Scenario 1)ETE and Trip Generation Summer, Midweek, Midday, Rain (Scenario 2)-Trip Generation 1ETE IA EU Z-100%80%60%40%20%0%___...NNNNNNMý 0 30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-2. ETE and Trip Generation:
Summer, Midweek, Midday, Rain (Scenario 2)Salem-Hope Creek NGS Evacuation Time Estimate J-10 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Summer, Weekend, Midday, Good (Scenario 3)-Trip Generation
-ETE Iq U Z M"8 4.0 100%80%60%40%20%0%0 30 60 90 120 150 180 210 240 270 300 330 Elapsed Time (min)Figure J-3. ETE and Trip Generation:
Summer, Weekend, Midday, Good Weather (Scenario 3)ETE and Trip Generation Summer, Weekend, Midday, Rain (Scenario 4)-Trip Generation mETE 100%In a, a, El 4-0 I-.4-0 4-C Ci U I..a, a.80%60%40%20%0%77 0 30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-4. ETE and Trip Generation:
Summer, Weekend, Midday, Rain (Scenario 4)Salem-Hope Creek NGS Evacuation Time Estimate J-11 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Summer, Midweek, Weekend, Evening, Good (Scenario 5)-Trip Generation -mETE IA (U'U Z-CL 100%80%60%40%20%0%0 30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-5. ETE and Trip Generation:
Summer, Midweek, Weekend, Evening, Good Weather (Scenario 5)ETE and Trip Generation Winter, Midweek, Midday, Good (Scenario 6)-Trip Generation mETE 100%In a'ap'U 0 I-S.-0 4.C a'U 1.a'0.80%60%40%20%0%ZOý.0ý , ý ý , -, , , ..0 30 60 90 120 150 180 Elapsed lime (min)210 240 270 300 330 Figure J-6. ETE and Trip Generation:
Winter, Midweek, Midday, Good Weather (Scenario 6)Salem-Hope Creek NGS Evacuation Time Estimate J-12 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Winter, Midweek, Midday, Rain (Scenario 7)-Trip Generation mETE a.'U 4-.0 I-.4-0 C a'U a'a-100%80%60%40%'.00ý201%0% 0 0 30 60 90 210 240 270 300 120 150 180 Elapsed Time (min)330 Figure J-7. ETE and Trip Generation:
Winter, Midweek, Midday, Rain (Scenario 7)ETE and Trip Generation Winter, Midweek, Midday, Snow (Scenario 8)-Trip Generation
-ETE 100%In a'£a'~4 U 4-0 I-*4~0 4-C a'U a'a.80%60%40%20%0%0 30 60 90 120 150 180 210 240 270 Elapsed Time (min)300 330 360 390 420 Figure J-8. ETE and Trip Generation:
Winter, Midweek, Midday, Snow (Scenario 8)Salem-Hope Creek NGS Evacuation Time Estimate J-13 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Winter, Weekend, Midday, Good (Scenario 9)-Trip Generation -ETE 4-0 0 4-.C 100%80%60%40%20%0%0 30 60 90 120 150 180 210 240 270 300 330 Elapsed Time (min)Figure J-9. ETE and Trip Generation:
Winter, Weekend, Midday, Good Weather (Scenario 9)ETE and Trip Generation Winter, Weekend, Midday, Rain (Scenario 10)-Trip Generation -ETE IA a'U a'(U 4-0 I-S.-0 C a'U I-a'0.100%80%60%40%20%0%0 30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-10. ETE and Trip Generation:
Winter, Weekend, Midday, Rain (Scenario 10)i-14 KLD Engineering, P.C.Salem-Hope Creek NGS Evacuation Time Estimate J-14 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Winter, Weekend, Midday, Snow (Scenario 11)-Trip Generation
-ETE In)", a, 4-0 100%80%60%40%20%0%0 30 60 90 120 150 180 210 240 270 300 330 360 390 420 Elapsed Time (min)Figure J-11. ETE and Trip Generation:
Winter, Weekend, Midday, Snow (Scenario 11)ETE and Trip Generation Winter, Midweek, Weekend, Evening, Good (Scenario 12)-Trip Generation
-ETE In a, a, tu 4-.0 I-0 4-C a, U 1~a, a.100%80%60%40%20%B mm//0% -I I I I I I I I ý I 0 30 60 90 120 150 180 210 240 270 300 330 Elapsed Time (min)Figure J-12. ETE and Trip Generation:
Winter, Midweek, Weekend, Evening, Good Weather (Scenario 12)Salem-Hope Creek NGS Evacuation Time Estimate J-15 KLD Engineering, P.C.Rev. 0 ETE and Trip Generation Summer, Weekend, Midday, Good, Special Event (Scenario 13)-Trip Generation 1ETE U, z a,'U 0 I-0 4-C a, U a, a.100%80%60%40%20%0%0 30 60 90 120 150 180 210 240 270 300 330 Elapsed Time (min)Figure J-13. ETE and Trip Generation:
Summer, Weekend, Midday, Good Weather, Special Event (Scenario 13)ETE and Trip Generation Summer, Midweek, Midday, Good, Roadway Impact (Scenario 14)-Trip Generation
-ETE 100%'A a,-o a,'U 4-0'4.-0 4-C a, U a, 0.80%60%40%20% L 0%0 IIIII I L _30 60 90 120 150 180 Elapsed Time (min)210 240 270 300 330 Figure J-14. ETE and Trip Generation:
Summer, Midweek, Midday, Good Weather, Roadway Impact (Scenario 14)Salem-Hope Creek NGS Evacuation Time Estimate J-16 KLD Engineering, P.C.Rev. 0