ML14118A012: Difference between revisions
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| number = ML14118A012 | | number = ML14118A012 | ||
| issue date = 04/25/2014 | | issue date = 04/25/2014 | ||
| title = | | title = 2013 10 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station | ||
| author name = Sindoni J M | | author name = Sindoni J M | ||
| author affiliation = PSEG Nuclear, LLC | | author affiliation = PSEG Nuclear, LLC | ||
Revision as of 21:58, 3 April 2019
| ML14118A012 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 04/25/2014 |
| From: | Sindoni J M Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N14-0112 | |
| Download: ML14118A012 (4) | |
Similar Documents at Salem, Hope Creek | |
|---|---|
Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024
[Table view]Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek 2024-02-05 Category:Report MONTHYEARML23335A1122023-12-15015 December 2023
[Table view]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 Category:Miscellaneous MONTHYEARML23335A1122023-12-15015 December 2023
[Table view]Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers 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-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments 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-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-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-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 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 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. 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, 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 ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. ML16256A6432016-07-18018 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 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 LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 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 ML14316A4092014-03-31031 March 2014 Well AA-V Installation Report - Table 5 Well Search Summary ML14316A4082014-03-31031 March 2014 Well AA-V Installation Report - Table 4 Mean Hydraulic Grad Study Results ML14316A4072014-03-31031 March 2014 Well AA-V Installation Report - Table 2 Groundwater Sample Analytical Results Vincentown Wells ML14316A4062014-03-31031 March 2014 Well AA-V Installation Report - Table 1 Well Construction Details ML14316A4032014-03-31031 March 2014 Well AA-V Installation Report - Table 3 Well AA-V Extended Purge Salem Chemistry Screening Results 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 ML14316A3982014-03-31031 March 2014 Well AA-V Installation Report - FIG-04 Monitoring Wells Screened within the Vincentown FORMATION-4 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 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 LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident 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, ... 2023-12-15 |
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