ML14316A408
ML14316A408 | |
Person / Time | |
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Site: | Salem |
Issue date: | 03/31/2014 |
From: | ARCADIS U.S. |
To: | Office of Nuclear Reactor Regulation, Public Service Enterprise Group |
Shared Package | |
ML14316A124 | List: |
References | |
LR-E14-0148 | |
Download: ML14316A408 (1) | |
Similar Documents at Salem | |
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Category:Report
MONTHYEARML23249A2622023-09-0606 September 2023
[Table view]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 Category:Miscellaneous MONTHYEARML21179A2352021-06-25025 June 2021
[Table view]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-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 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 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 ML14113A2212014-04-30030 April 2014 NRC Staff Review of the Documentation Provided by PSEG Nuclear LLC for the Salem Generating Station Units 1 and 2 Concerning Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station ML14316A4022014-03-31031 March 2014 Well AA-V Installation Report - FIG-06 Potable Well Locations in Lower Alloways Creek Elsinboro and Greenwich Townships ML14316A4012014-03-31031 March 2014 Well AA-V Installation Report - FIG-05 Vincentown Formation Mean Hydraulic Fluctuation Study Results Map - August 2013-5 ML14316A4002014-03-31031 March 2014 Well AA-V Installation Report - FIG-02 Regional Cross SECTION-2 ML14316A3972014-03-31031 March 2014 Well AA-V Installation Report - FIG-03 Facility Cross Section Through AA-V-3 ML14316A3792014-03-31031 March 2014 Well AA-V Installation Report - Appendix a - Monitoring Well Certification Form B ML14316A3982014-03-31031 March 2014 Well AA-V Installation Report - FIG-04 Monitoring Wells Screened within the Vincentown FORMATION-4 ML14316A3692014-03-31031 March 2014 Final Well AA-V Installation Report 031214 ML14316A3342014-03-31031 March 2014 Well AA-V Installation Report - Appendix F - Well Search Results ML14316A3332014-03-31031 March 2014 Well AA-V Installation Report - Appendix E - Summary, Charts and Raw Data ML14316A3312014-03-31031 March 2014 Well AA-V Installation Report - Appendix D Specific Capacity Test for Well AA-V ML14316A3292014-03-31031 March 2014 Well AA-V Installation Report - Appendix C - AA-V Construction and Boring Logs ML14316A3282014-03-31031 March 2014 Well AA-V Installation Report - Appendix B - Cb Abandonment Report ML14316A4062014-03-31031 March 2014 Well AA-V Installation Report - Table 1 Well Construction Details ML14316A4072014-03-31031 March 2014 Well AA-V Installation Report - Table 2 Groundwater Sample Analytical Results Vincentown Wells ML14316A4032014-03-31031 March 2014 Well AA-V Installation Report - Table 3 Well AA-V Extended Purge Salem Chemistry Screening Results ML14316A4082014-03-31031 March 2014 Well AA-V Installation Report - Table 4 Mean Hydraulic Grad Study Results ML14316A4092014-03-31031 March 2014 Well AA-V Installation Report - Table 5 Well Search Summary LR-N13-0259, Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22)2013-11-0404 November 2013 Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22) LR-N13-0083, Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ...2013-04-26026 April 2013 Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ... LR-N13-0040, In-Service Inspection Activities - 90-Day Report, Revision 12013-03-0101 March 2013 In-Service Inspection Activities - 90-Day Report, Revision 1 IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML11203A0782011-07-13013 July 2011 Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6 LR-N11-0090, 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations2011-04-0808 April 2011 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations ML1029800892010-10-21021 October 2010 Steam Generator Tube Inspection Report- Twentieth Refueling Outage (1 R20) 2021-06-25 |
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Table 4: Mean Hydraulic Gradient Study Results Well AA-V Installation Report PSEG Nuclear, LLC, Salem Generating Station, Hancocks Bridge, New Jersey Mean based on Serfes Standard Error Maximum Value Minimum Value Arithmetic Mean Location ID (1991) ft amsl ft amsl ft amsl ft amsl ft amsl Well AA-V 0.63 0.017 2.50 -1.29 0.70 Well K 1.36 0.005 1.96 0.80 1.40 Well L 0.65 0.016 2.47 -1.22 0.73 Well P 0.98 0.016 2.78 -0.88 1.04 Well Q 1.79 0.0004 2.07 1.75 1.80 Well V 1.55 0.005 2.19 0.94 1.59 Delaware River 0.88 0.025 4.25 -2.74 0.96 Notes:
ft amsl: Feet above mean sea level (NAVD 88)
Table 4 Mean Hydra Grad Study Results.xls 1 of 1