LR-N06-0180, Special Report, Main Steam Line Monitor Inoperable Greater than 7 Days
ML061290580 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 04/28/2006 |
From: | Joyce T Public Service Enterprise Group |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
LR-N06-0180 | |
Download: ML061290580 (3) | |
Similar Documents at Salem | |
---|---|
Category:Letter type:LR
MONTHYEARLR-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
[Table view]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 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 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 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 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities 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 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 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-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report 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-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08 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:Technical 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 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 |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG APR 2 8 2006 NuclearLLC LR-N06-01 80 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SPECIAL REPORT MAIN STEAM LINE MONITOR INOPERABLE GREATER THAN 7 DAYS SALEM - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This special report is being submitted pursuant to the requirements of Salem Unit 2 Technical Specification (TS) 3.3.3.1, which requires one Main Steam Line Radiation Monitor per steam line. Action statement 3.3.3.1.b requires that action be taken to restore an inoperable radiation monitor channel within seven (7)days, and to submit a Special Report pursuant to TS 6.9.2, if unsuccessful.
The design of the Main Steam Line Radiation Monitors consists of one detector per steam line (R46A-D), and a common detector (R46E) capable of monitoring any of the four main steam lines. These detectors receive process flow from the main steam lines, which is cooled by chilled water and monitored by the detector.
The common detector (R46E) has been inoperable due to leakage into the detector.
The detector and its instrument drawer were sent to the vendor for repairs. Although this channel has been inoperable, the TS requirements were maintained by detectors R46A-D.
Channel R46C was declared inoperable on April 10, 2006 to perform planned elective maintenance to repair a minor steam leak on a solenoid valve. During the course of this corrective maintenance, it was determined that a section of steam piping on the detector needed to be replaced. Although not part of the original job scope, the pipe integrity was critical to returning R46C an to operable status.
The additional piping to support repairs to the R46C was obtained and the detector was repaired, retested and declared OPERABLE on April 21, 2006. Investigation as to why the pipe was not available to support repairs is ongoing and has been entered into the station's Corrective Action Program.
95-2168 REV. 7/99
'PR 2 8 2006 Document Control Desk LR-N06-01 80 The repaired R46E detector and instrument drawer are scheduled to be returned from the vendor in June 2006. The current design of the Main Steam Line Radiation Monitors is an obsolete, antiquated design that routes main steam flow to a detector.
The station is planning to install a new "dry system" design that is attached external to the main steam piping. This system is expected to be more reliable. It is anticipated that this design change will be installed in September 2006.
This special report contains no commitments. If you have any questions on this report, please contact Justin Wearne at (856) 339-5081.
Sincerely, Thomas P. oyce Site Vice President - Salem
APR 2 8 2006 Document Control Desk LR-N06-01 80 C: Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625