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Category:Calculation
MONTHYEARLR-N17-0044, Enclosure 14 O LR-N17-0044 and LAR H17-03 - Calculation SC-BB-0525, Hope Creek Heat Balance Uncertainty Calculation, Revision 52017-03-16016 March 2017 Enclosure 14 O LR-N17-0044 and LAR H17-03 - Calculation SC-BB-0525, Hope Creek Heat Balance Uncertainty Calculation, Revision 5 ML17188A2692017-03-16016 March 2017 Enclosure 14 O LR-N17-0044 and LAR H17-03 - Calculation SC-BB-0525, Hope Creek Heat Balance Uncertainty Calculation, Revision 5 ML15030A2422014-09-22022 September 2014 Appendix a, Mass Flux Calculations ML12284A4272012-10-0404 October 2012 PSEG Early Site Permit Application, Calculation of Multiplier Effects for Er Section 10.4 ML1034404512010-04-23023 April 2010 Document: Ansys Input Files and Calculation Package Drafts LR-N10-0355, Offsite Dose Calculation Manual, Rev. 25 for Pseg Nuclear LLC Salem Generating Station2010-04-16016 April 2010 Offsite Dose Calculation Manual, Rev. 25 for Pseg Nuclear LLC Salem Generating Station ML1100701702010-04-16016 April 2010 Offsite Dose Calculation Manual, Rev. 25 for PSEG Nuclear LLC Salem Generating Station LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 252010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504172010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1013003732009-10-27027 October 2009 Attachment 1, Offsite Dose Calculation Manual Revision, 24 LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual Revision, 242009-10-27027 October 2009 Salem - Attachment 1, Offsite Dose Calculation Manual Revision, 24 LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 232009-08-0606 August 2009 Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23 ML1013003712009-08-0606 August 2009 Attachment 1, Offsite Dose Calculation Manual, Revision 23 LR-N10-0355, Hope Creek, CC-AA-309-1001, Rev. 3, Hc Class 1E 125 Vdc Station Battery & Charger Sizing2009-08-0505 August 2009 Hope Creek, CC-AA-309-1001, Rev. 3, Hc Class 1E 125 Vdc Station Battery & Charger Sizing ML1100504142009-08-0505 August 2009 Hope Creek, CC-AA-309-1001, Rev. 3, Hc Class 1E 125 Vdc Station Battery & Charger Sizing LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 222009-06-0909 June 2009 Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22 ML1013003702009-06-0909 June 2009 Attachment 1, Offsite Dose Calculation Manual, Revision 22 LR-N09-0099, Annual Radioactive Effluent Release Report, Page 181 Through End2009-05-31031 May 2009 Annual Radioactive Effluent Release Report, Page 181 Through End LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 1802009-05-31031 May 2009 Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180 ML0912803782009-05-31031 May 2009 Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180 LR-N09-0074, Letter from Jeffrie Keenan of PSEG Nuclear L.L.C., NRC Decommissioning Funding Status Report for Salem, Hope Creek & Peach Bottom Generating Stations2009-03-31031 March 2009 Letter from Jeffrie Keenan of PSEG Nuclear L.L.C., NRC Decommissioning Funding Status Report for Salem, Hope Creek & Peach Bottom Generating Stations ML0821104192008-07-23023 July 2008 Calculation S-1-FHV-MDC-0705, Revision 5, Fhv System Heating and Cooling and Air Flow Determination. ML0708711122007-02-19019 February 2007 Calculation 0108-0342-JFL-01, Rev 0, Analysis of CCW Supply Temperature During LOCA Recirculation. ML0707906522007-02-14014 February 2007 Calculation S-C-SF-MDC-1810, Rev 7, Decay Heat-up Rates and Curves. ML0622303242006-05-18018 May 2006 Attachment 6, Calculation S-C-ZZ-MDC-1920, Rev. 41R0, 'Fuel Handling Accident Radiological Consequences Evaluation. ' ML0526502192005-09-13013 September 2005 Rev. 0 to Calculation 0108-0236-01 LR-N05-0424, Attachment 1, Calculation S-1-SJ-MDC-1539, Revision 2, Accumulator Pressure Decay Time During Discharge Test.2005-08-12012 August 2005 Attachment 1, Calculation S-1-SJ-MDC-1539, Revision 2, Accumulator Pressure Decay Time During Discharge Test. LR-N08-0308, Attachment 3 - Salem, Units 1 and 2 - Calculation S-2-SJ-MDC-1394, Rev. 5, Accumulator Pressure Decay Time During Discharge Test.2005-07-20020 July 2005 Attachment 3 - Salem, Units 1 and 2 - Calculation S-2-SJ-MDC-1394, Rev. 5, Accumulator Pressure Decay Time During Discharge Test. LR-N04-0413, Waste Gas Decay Tank and Volume Control Tank Rupture Accidents - AST Analysis2003-11-10010 November 2003 Waste Gas Decay Tank and Volume Control Tank Rupture Accidents - AST Analysis ML19030A7321978-02-10010 February 1978 Enclosed Calculations on Pressurizer Overpressure Protection System (Pops) 2017-03-16
[Table view] Category:Report
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 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-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 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-N17-0076, Focused Evaluation of External Flooding2017-06-30030 June 2017 Focused Evaluation of External Flooding 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-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-30030 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16280A5232016-08-31031 August 2016 Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review 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 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 ML15030A1632014-09-22022 September 2014 Remedial Action Progress Report First Quarter 2014 ML15030A2422014-09-22022 September 2014 Appendix a, Mass Flux Calculations ML15030A2432014-09-22022 September 2014 Figure 1, Site Location Map ML15030A2442014-09-22022 September 2014 Figure 2, Station Layout Map ML15030A2832014-09-22022 September 2014 Table 01, Well Construction Details ML15030A2452014-09-22022 September 2014 Figure 3, Salem Generating Station Layout Map ML15030A2462014-09-22022 September 2014 Figure 4, Station Shallow Groundwater Elevation Contours - February 2014 ML15030A2472014-09-22022 September 2014 Figure 5, Salem Generating Station Hydrogeologic Cross Section A-A' ML15030A2482014-09-22022 September 2014 Figure 6, Salem Generating Station Hydrogeologic Cross Section B-B' ML15030A2492014-09-22022 September 2014 Figure 7, Salem Generating Station Hydrogeologic Cross Section C-C' ML15030A2502014-09-22022 September 2014 Figure 8,Salem Generating Station Hydrogeologic Cross Section D-D' ML15030A2752014-09-22022 September 2014 Figure 10, Precipitation Measurements ML15030A3012014-09-22022 September 2014 Table 08, Unit 2 Seismic Gap Drain Tritium Analytical Results ML15030A3002014-09-22022 September 2014 Table 07, Unit 1 Seismic Gap Drain Tritium Analytical Results ML15030A2992014-09-22022 September 2014 Table 06B, Groundwater Analytical Results for Well AC ML15030A2982014-09-22022 September 2014 Table 06A, Groundwater Tritium Analytical Results for Well AC ML15030A2962014-09-22022 September 2014 Table 05, Groundwater Analytical Results (1.22.2003 Through 3.31.2014) ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2842014-09-22022 September 2014 Table 02, Sample Collection Schedule - First & Second Quarter 2014 ML15030A2822014-09-22022 September 2014 Figure 16, Salem Unit 2 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2812014-09-22022 September 2014 Figure 15, Salem Unit 1 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2802014-09-22022 September 2014 Figure 14, Historic Tritium Recovered Through Well Field Operation ML15030A2792014-09-22022 September 2014 Figure 13, Tritium Isoconcentration Map - March 2014 ML15030A2762014-09-22022 September 2014 Figure 11, Station Wind Summary - Q1 2014 ML15030A2512014-09-22022 September 2014 Figure 9, Salem Generating Station Hydrogeologic Cross Section E-E' 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 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) ML16280A5232016-08-31031 August 2016 Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review ML15030A3012014-09-22022 September 2014 Table 08, Unit 2 Seismic Gap Drain Tritium Analytical Results ML15030A1632014-09-22022 September 2014 Remedial Action Progress Report First Quarter 2014 ML15030A2422014-09-22022 September 2014 Appendix a, Mass Flux Calculations ML15030A2432014-09-22022 September 2014 Figure 1, Site Location Map ML15030A2442014-09-22022 September 2014 Figure 2, Station Layout Map ML15030A2452014-09-22022 September 2014 Figure 3, Salem Generating Station Layout Map ML15030A2462014-09-22022 September 2014 Figure 4, Station Shallow Groundwater Elevation Contours - February 2014 ML15030A2482014-09-22022 September 2014 Figure 6, Salem Generating Station Hydrogeologic Cross Section B-B' ML15030A3002014-09-22022 September 2014 Table 07, Unit 1 Seismic Gap Drain Tritium Analytical Results ML15030A2992014-09-22022 September 2014 Table 06B, Groundwater Analytical Results for Well AC ML15030A2982014-09-22022 September 2014 Table 06A, Groundwater Tritium Analytical Results for Well AC ML15030A2962014-09-22022 September 2014 Table 05, Groundwater Analytical Results (1.22.2003 Through 3.31.2014) ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2842014-09-22022 September 2014 Table 02, Sample Collection Schedule - First & Second Quarter 2014 ML15030A2832014-09-22022 September 2014 Table 01, Well Construction Details ML15030A2822014-09-22022 September 2014 Figure 16, Salem Unit 2 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2812014-09-22022 September 2014 Figure 15, Salem Unit 1 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2802014-09-22022 September 2014 Figure 14, Historic Tritium Recovered Through Well Field Operation ML15030A2472014-09-22022 September 2014 Figure 5, Salem Generating Station Hydrogeologic Cross Section A-A' ML15030A2492014-09-22022 September 2014 Figure 7, Salem Generating Station Hydrogeologic Cross Section C-C' ML15030A2502014-09-22022 September 2014 Figure 8,Salem Generating Station Hydrogeologic Cross Section D-D' ML15030A2512014-09-22022 September 2014 Figure 9, Salem Generating Station Hydrogeologic Cross Section E-E' ML15030A2752014-09-22022 September 2014 Figure 10, Precipitation Measurements ML15030A2762014-09-22022 September 2014 Figure 11, Station Wind Summary - Q1 2014 ML15030A2792014-09-22022 September 2014 Figure 13, Tritium Isoconcentration Map - March 2014 ML14010A3432014-01-13013 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Salem Generating Station, Units 1 and 2, TAC Nos.: MF0868 and MF0869 LR-N13-0172, Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2013-12-20020 December 2013 Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic LR-N13-0122, Steam Generator Tube Inspection Report - Nineteenth Refueling Outage (2R19)2013-05-0909 May 2013 Steam Generator Tube Inspection Report - Nineteenth Refueling Outage (2R19) LR-N13-0020, SL-011677, Rev 3, Reliable Spent Fuel Pool Instrumentation Overall Integrated Plan2013-02-25025 February 2013 SL-011677, Rev 3, Reliable Spent Fuel Pool Instrumentation Overall Integrated Plan LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N2012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N 2023-09-06
[Table view] Category:Status Report
MONTHYEARML22076A0502022-03-17017 March 2022 and Salem Generating Station, Units 1 and 2 - Annual Property Insurance Status Report LR-N21-0015, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-03-25025 March 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N19-0014, Stations - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2019-03-25025 March 2019 Stations - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N18-0041, Annual Property Insurance Status Report2018-04-0505 April 2018 Annual Property Insurance Status Report RS-17-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-30030 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N17-0043, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-29029 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N17-0041, Annual Property Insurance Status Report2017-03-24024 March 2017 Annual Property Insurance Status Report LR-N16-0043, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-29029 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) LR-N15-0167, PSEG Nuclear Llc'S Fifth Six-Month Status Report for the Salem Generating Station in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA2015-08-26026 August 2015 PSEG Nuclear Llc'S Fifth Six-Month Status Report for the Salem Generating Station in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12 NL-15-1620, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-08-26026 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) LR-N15-0048, Salem, Units 1 and 2, Hope Creek - Annual Property Insurance Status Report2015-03-30030 March 2015 Salem, Units 1 and 2, Hope Creek - Annual Property Insurance Status Report ML15089A4262015-03-30030 March 2015 Annual Property Insurance Status Report LR-N15-0023, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2015-02-18018 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) ML15051A2702015-02-18018 February 2015 PSEG Nuclear Llc'S Fourth Six-Month Status Report for the Salem Generating Station in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-1 ML15030A2472014-09-22022 September 2014 Figure 5, Salem Generating Station Hydrogeologic Cross Section A-A' ML15030A1632014-09-22022 September 2014 Remedial Action Progress Report First Quarter 2014 ML15030A2422014-09-22022 September 2014 Appendix a, Mass Flux Calculations ML15030A2432014-09-22022 September 2014 Figure 1, Site Location Map ML15030A2442014-09-22022 September 2014 Figure 2, Station Layout Map ML15030A2452014-09-22022 September 2014 Figure 3, Salem Generating Station Layout Map ML15030A2462014-09-22022 September 2014 Figure 4, Station Shallow Groundwater Elevation Contours - February 2014 ML15030A2482014-09-22022 September 2014 Figure 6, Salem Generating Station Hydrogeologic Cross Section B-B' ML15030A2492014-09-22022 September 2014 Figure 7, Salem Generating Station Hydrogeologic Cross Section C-C' ML15030A2502014-09-22022 September 2014 Figure 8,Salem Generating Station Hydrogeologic Cross Section D-D' ML15030A2752014-09-22022 September 2014 Figure 10, Precipitation Measurements 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 ML15030A3012014-09-22022 September 2014 Table 08, Unit 2 Seismic Gap Drain Tritium Analytical Results ML15030A2512014-09-22022 September 2014 Figure 9, Salem Generating Station Hydrogeologic Cross Section E-E' ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2842014-09-22022 September 2014 Table 02, Sample Collection Schedule - First & Second Quarter 2014 ML15030A2832014-09-22022 September 2014 Table 01, Well Construction Details ML15030A2822014-09-22022 September 2014 Figure 16, Salem Unit 2 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2812014-09-22022 September 2014 Figure 15, Salem Unit 1 - Tritium Concentrations in Water Recovered Through Seismic Gap Drain Operation ML15030A2802014-09-22022 September 2014 Figure 14, Historic Tritium Recovered Through Well Field Operation ML15030A2792014-09-22022 September 2014 Figure 13, Tritium Isoconcentration Map - March 2014 ML15030A2762014-09-22022 September 2014 Figure 11, Station Wind Summary - Q1 2014 LR-N14-0187, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-26026 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) LR-N14-0033, PSEG Nuclear Llc'S Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation Order Number EA-12-051)2014-02-25025 February 2014 PSEG Nuclear Llc'S Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation Order Number EA-12-051) LR-N14-0027, PSEG Nuclear Llc'S Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2014-02-25025 February 2014 PSEG Nuclear Llc'S Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) LR-N13-0175, PSEG Nuclear Llc'S First Six-Month Status Report for the Salem in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-2013-08-25025 August 2013 PSEG Nuclear Llc'S First Six-Month Status Report for the Salem in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12- LR-N13-0176, PSEG Nuclear Llc'S First Six-Month Status Report for Salem in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)2013-08-25025 August 2013 PSEG Nuclear Llc'S First Six-Month Status Report for Salem in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors LR-N13-0059, NRC Decommissioning Funding Status Report2013-03-26026 March 2013 NRC Decommissioning Funding Status Report LR-N12-0329, PSEG Nuclear Llc'S Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2012-10-31031 October 2012 PSEG Nuclear Llc'S Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) LR-N12-0331, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051)2012-10-31031 October 2012 Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051) LR-N12-0087, Annual Property Insurance Status Report2012-03-21021 March 2012 Annual Property Insurance Status Report 2022-03-17
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Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells BB AHD Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 144 ft Volumetric Flux (Q) 82.5663722 ft^3/d Q = K*i*b*w Average Concentration (C) 503 pCi/L Maximum shallow concentration Mass Flux (M) 1,176,024 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 144 ft Volumetric Flux (Q) 18.7650846 ft^3/d Q = K*i*b*w Average Concentration (C) 503 pCi/L Maximum shallow concentration Mass Flux (M) 267,278 pCi/d M = Q*C HF+RD= 1,443,302 pCi/d HF+RD= 0.0005 Ci/yr Mass Flux Between Wells AHD AGD Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 99 ft Volumetric Flux (Q) 56.7981887 ft^3/d Q = K*i*b*w Average Concentration (C) 589 pCi/L Average shallow concentration Mass Flux (M) 947,852 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 99 ft Volumetric Flux (Q) 12.9086793 ft^3/d Q = K*i*b*w Average Concentration (C) 589 pCi/L Average shallow concentration Mass Flux (M) 215,421 pCi/d M = Q*C HF+RD= 1,163,273 pCi/d HF+RD= 0.0004 Ci/yr
Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells AGD Z Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 215 ft Volumetric Flux (Q) 122.8216 ft^3/d Q = K*i*b*w Average Concentration (C) 702 pCi/L Average shallow concentration Mass Flux (M) 2,441,500 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 215 ft Volumetric Flux (Q) 27.9140001 ft^3/d Q = K*i*b*w Average Concentration (C) 702 pCi/L Average shallow concentration Mass Flux (M) 554,886 pCi/d M = Q*C HF+RD= 2,996,387 pCi/d HF+RD= 0.0011 Ci/yr Mass Flux Between Wells Z Y Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 106 ft Volumetric Flux (Q) 60.632 ft^3/d Q = K*i*b*w Average Concentration (C) 728 pCi/L Maximum shallow concentration Mass Flux (M) 1,250,481 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 106 ft Volumetric Flux (Q) 13.78 ft^3/d Q = K*i*b*w Average Concentration (C) 728 pCi/L Maximum shallow concentration Mass Flux (M) 284,200 pCi/d M = Q*C HF+RD= 1,534,681 pCi/d HF+RD= 0.0006 Ci/yr
Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells Y BC Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 83 ft Volumetric Flux (Q) 47.3966807 ft^3/d Q = K*i*b*w Average Concentration (C) 357 pCi/L Maximum shallow concentration Mass Flux (M) 479,138 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 83 ft Volumetric Flux (Q) 10.7719729 ft^3/d Q = K*i*b*w Average Concentration (C) 357 pCi/L Maximum shallow concentration Mass Flux (M) 108,895 pCi/d M = Q*C HF+RD= 588,034 pCi/d HF+RD= 0.0002 Ci/yr Mass Flux Between Wells BC BE Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 279 ft Volumetric Flux (Q) 159.513151 ft^3/d Q = K*i*b*w Average Concentration (C) 378 pCi/L Average shallow concentration Mass Flux (M) 1,705,133 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 279 ft Volumetric Flux (Q) 36.2529888 ft^3/d Q = K*i*b*w Average Concentration (C) 378 pCi/L Average shallow concentration Mass Flux (M) 387,530 pCi/d M = Q*C HF+RD= 2,092,664 pCi/d HF+RD= 0.0008 Ci/yr
Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells BE BG Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 706 ft Volumetric Flux (Q) 403.840507 ft^3/d Q = K*i*b*w Average Concentration (C) 408 pCi/L Average shallow concentration Mass Flux (M) 4,665,680 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 706 ft Volumetric Flux (Q) 91.7819334 ft^3/d Q = K*i*b*w Average Concentration (C) 408 pCi/L Average shallow concentration Mass Flux (M) 1,060,382 pCi/d M = Q*C HF+RD= 5,726,062 pCi/d HF+RD= 0.0021 Ci/yr Mass Flux Between Wells BG BH Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 464 ft Volumetric Flux (Q) 265.499208 ft^3/d Q = K*i*b*w Average Concentration (C) 418 pCi/L Maximum shallow concentration Mass Flux (M) 3,142,566 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 464 ft Volumetric Flux (Q) 60.3407292 ft^3/d Q = K*i*b*w Average Concentration (C) 418 pCi/L Maximum shallow concentration Mass Flux (M) 714,220 pCi/d M = Q*C HF+RD= 3,856,785 pCi/d HF+RD= 0.0014 Ci/yr
Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells BH BK Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 454 ft Volumetric Flux (Q) 259.92035 ft^3/d Q = K*i*b*w Average Concentration (C) 233 pCi/L Maximum shallow concentration Mass Flux (M) 1,714,909 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 454 ft Volumetric Flux (Q) 59.0728068 ft^3/d Q = K*i*b*w Average Concentration (C) 233 pCi/L Maximum shallow concentration Mass Flux (M) 389,752 pCi/d M = Q*C HF+RD= 2,104,661 pCi/d HF+RD= 0.0008 Ci/yr Mass Flux Between Wells BK BL Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 366 ft Volumetric Flux (Q) 209.249609 ft^3/d Q = K*i*b*w Average Concentration (C) 233 pCi/L Maximum shallow concentration Mass Flux (M) 1,380,592 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 366 ft Volumetric Flux (Q) 47.5567293 ft^3/d Q = K*i*b*w Average Concentration (C) 233 pCi/L Maximum shallow concentration Mass Flux (M) 313,771 pCi/d M = Q*C HF+RD= 1,694,363 pCi/d HF+RD= 0.0006 Ci/yr
Appendix A: Mass Flux Calculations Shallow, Water Bearing Unit PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells BL BO Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 647 ft Volumetric Flux (Q) 369.834605 ft^3/d Q = K*i*b*w Average Concentration (C) 329 pCi/L Maximum shallow concentration Mass Flux (M) 3,448,960 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 647 ft Volumetric Flux (Q) 84.0533194 ft^3/d Q = K*i*b*w Average Concentration (C) 329 pCi/L Maximum shallow concentration Mass Flux (M) 783,854 pCi/d M = Q*C HF+RD= 4,232,814 pCi/d HF+RD= 0.0015 Ci/yr Mass Flux Between Wells BO BP Hydraulic and Structural Fill Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 22 ft xsect EE' Plume or Unit Width (w) 463 ft Volumetric Flux (Q) 264.614149 ft^3/d Q = K*i*b*w Average Concentration (C) 329 pCi/L Maximum shallow concentration Mass Flux (M) 2,465,210 pCi/d M = Q*C Riverbed Deposits Source Average Hydraulic Conductivity (K) 6.5 ft/d Groundwater Flow Model Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 5 ft xsect EE' Plume or Unit Width (w) 463 ft Volumetric Flux (Q) 60.1395793 ft^3/d Q = K*i*b*w Average Concentration (C) 329 pCi/L Maximum shallow concentration Mass Flux (M) 560,275 pCi/d M = Q*C HF+RD= 3,025,484 pCi/d HF+RD= 0.0011 Ci/yr Total Shallow Water Bearing Unit = 0.0111 Ci/yr
- Mass Flux Calculations Deeper Groundwater PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey
= input
= computed Mass Flux Between Wells P AAV Basal Sand Source Average Hydraulic Conductivity (K) 5 ft/d Dames & Moore May 23, 1974 Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 18 ft xsect EE' Plume or Unit Width (w) 519 ft based on P and AAV well locations Volumetric Flux (Q) 187.02 ft^3/d Q = K*i*b*w Average Concentration (C) 7,753 pCi/L Maximum concentration Mass Flux (M) 41,055,267 pCi/d M = Q*C Vincentown Formation Source Average Hydraulic Conductivity (K) 11.34 ft/d Estimated from the 2013 Well AAV specific capacity test (ARCADIS 2014)
Average Hydraulic Gradient (i) 0.0051 ft/ft Estimated from the 2013 mean hydraulic gradient study (ARCADIS 2014)
Average Saturated Thickness (b) 20 ft xsect EE' and Appendix B, upper third of full thickness Plume or Unit Width (w) 519 ft based on P and AAV well locations Volumetric Flux (Q) 600.89 ft^3/d Q = K*i*b*w Average Concentration (C) 7,753 pCi/L Maximum concentration Mass Flux (M) 131,910,573 pCi/d M = Q*C KW + Vin = 172,965,840 pCi/d KW + Vin = 0.0631 Ci/yr Mass Flux Between Wells AAV L Basal Sand Source Average Hydraulic Conductivity (K) 5 ft/d Dames & Moore May 23, 1974 Average Hydraulic Gradient (i) 0.004 ft/ft Estimated from Remedial Investigation Report (ARCADIS 2004a) Appendix B (not specific for this unit)
Average Saturated Thickness (b) 18 ft xsect EE' Plume or Unit Width (w) 442 ft based on AAV and L well locations Volumetric Flux (Q) 159.003079 ft^3/d Q = K*i*b*w Average Concentration (C) 7,753 pCi/L Maximum concentration Mass Flux (M) 34,905,366 pCi/d M = Q*C Vincentown Formation Source Average Hydraulic Conductivity (K) 11.34 ft/d Estimated from the 2013 Well AAV specific capacity test (ARCADIS 2014)
Average Hydraulic Gradient (i) 0.0051 ft/ft Estimated from the 2013 mean hydraulic gradient study (ARCADIS 2014)
Average Saturated Thickness (b) 20 ft xsect EE' and Appendix B, upper third of full thickness Plume or Unit Width (w) 442 ft based on AAV and L well locations Volumetric Flux (Q) 510.876894 ft^3/d Q = K*i*b*w Average Concentration (C) 7,753 pCi/L Maximum concentration Mass Flux (M) 112,150,941 pCi/d M = Q*C KW + Vin = 147,056,308 pCi/d KW + Vin = 0.0537 Ci/yr Total Deeper Groundwater= 0.117 Ci/yr TOTAL MASS FLUX = 0.128 Ci/yr