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Category:Letter
MONTHYEARIR 05000272/20240032024-10-30030 October 2024 Integrated Inspection Report 05000272/2024003 and 05000311/2024003 ML24296B1932024-10-23023 October 2024 Project Manager Assignment LR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024 Core Operating Limits Report - Cycle 28 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) IR 05000272/20244032024-09-25025 September 2024 And Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) ML24267A1082024-09-23023 September 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) IR 05000272/20240052024-08-29029 August 2024 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005) IR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 05000272/LER-2024-001, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024 Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML24071A2132024-03-12012 March 2024 Senior Reactor and Reactor Operator Initial License Examinations LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024 Spent Fuel Cask Registration IR 05000272/20230062024-02-28028 February 2024 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006 IR 05000272/20244012024-02-26026 February 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 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 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection 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 ML24250A0582023-11-14014 November 2023 PSEG to Marine Mammal Stranding Center, Salem Sea Turtle Stranding Response Services IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 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) 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) 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 2024-09-25
[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] |
Text
PS~G e Public Service Electric and Gas Co*mpany 80 Park Place Newark, N.J. 07101 Phone 201 /622-7000 July 19, 1976 H\egulatory Docket File Gentlemen:
REQUEST FOR EXEMPTION 10 CFR 50.55a NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 PSE&G hereby transmits a tabulation of those pumps and valves which we have determined to be subject to the requirements of 10 CFR 50.55a (g). Enclosures 1 and 2 identify, respectively, each pump and valve that is subject to the aforementioned requirements. In addition, those pumps and valves for which conformance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code is impractical are S<? i.dent.ified.
It is hereby requested that exemption to those code requirements identified in the enclosures be granted for Unit 1 of the Salem facility.
Very truly yours,
?-f~if/
R. L. Mittl General Manager - Projects Engineering and Construction Department The Energy People 95-2001 (250M) 12-73
-.~
- e ENCLOSURE I Inservice Testing ASME Code Class 1, 2 and 3 Pumps No. 1 unit Salem Nuclear Generating Station The following is a tabulation of pumps that are subject to the inservice testing requirements as set forth in 10 CFR 50.55a (g);
for those pumps, identified in the tabulation, where the specific provisions of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Winter, 1975, cannot be complied with, exemption is hereby requested in* accordance with 10 CFR 50.55a (g) (5) o Exemption Pump Requested Remarks*
- 1. Auxi~iary Feedwater Pump No. 11 Yes No provision has been made for measurement of:
- a. Flow rate (Q)
- 2. Auxiliary Feedwater Pump No. 12 Yes Same as (1)
- 3. Containment Spray Pump No. 11 No .*.None
- 4. Containment Spray Pump No. 12 No None
- 5. Service Water Pump No. 11 Yes No provision has been made for measurement of:
- a. Inlet Pressure (Pi)
- b. Differential Pressure ( il P)
- c. Flow rate (Q) d .. Lubricant Level or pressure
- 6. Service Water Pump No. 12 Yes Same as (5)
':*. 1 I . I ' : I : 11 J ' *'
1
' ' ~I f l : ') I I \ ' ' I' L; \
- I *, ' ' I I I I I* I I; ' : .~ 1 *
\
,.* En.closure I . . "l Exemption Requested Remarks*
- 7. Service Water Pump No. 13 Yes Same as (5)
- 8. Service Water Pump No. 14 Yes Same as (5)
- 9. Service Water Pump No.* 15 .Yes Same as (5)
- 10. Service Water Pump No. 16 Yes Same as (5)
- 11. Safety Injection Pump No. 11 No None
- 12. Safety Injection Pump No. 12 No None
- 13. Component Cooling Pump No. 11 Yes No. provision has been made for measurement of:
- a. Flow rate {Q)
- 14. Component Cooling Pump No. 12 Yes Same as (13)
- 15. Component Cooling Pump No. 13 Yes Same as (13)
- 16. Charging Pump No. 11 Yes No provision has been made for measurement of:
- a. *Flow rate (Q)
- 17. Charging pump No. 12 Yes Same as (16)
- 18. Charging Pump No. 13 None
- 19. BA Transfer Pump No. 11 Yes No provision has been made for measurement of:*
- a. Inlet Pressur~ (Pi)
- b. Differential Pressure (6 P)
- c. Flow rate (Q)
- 20. BA Transfer Pump Noo 12 Yes Same c=i.s (19)
En6losure I Exemption Pump Reguested Remarks*
- 21. Chilled water Pump No. 11 Yes No provision has been made for measurement of: *
- a. Inl~t Pressure (P.)
l.
- b. Flow Rate (Q)
- 22. Chilled Water Pump No. 12 Yes Same as ( 21)
- 23. RHR Pump No. 11 No None
- 24. RHR Pump No. 12 No None
- Parameters identified refer to those parameters listed in Table IWP-3100-1 of Section XI of the ASME Boiler and Pressure Vessel Code.
- / l' I : ' ' t ' , I ' " " I *: ** 1* ' * *" I 1 \ "
- I ,1 \ r ' ' , f' '" ! 1r ' ' ' ', !* ' ~ I ** , I ' \1 * " ' ~ ' ** *
- ENCLOSURE 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves No. 1 Unit Salem Nuclear Generating Station The following is a tabulation of valves that are subject to the inservice testing requirements as set forth in 10 CFR 50.55a (g),
for those valves, identifed in the tabulation, where the specific provisions of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Winter 1975 cannot be complied with exemption is hereby requested in accordance with 10 CFR 50.55a (g) (5).
Exemption Valve Requested Remarks Safety Injection System 1 SJ 1 No 1 SJ 2 No 1 SJ 3 No 1 SJ 4 No 1 SJ 5 No 1 SJ 10 No 1 SJ 12 No 1 SJ 13 No 11 SJ 16 No 12 SJ 16 No 13 SJ 16 No 14 SJ 16 No 11 SJ 17 No 12 SJ 17 No 13 SJ 17 No 14 SJ 17 No 11 SJ 29 No
-*~-rr*-r;T"'."rr,.,r.r*-*r~ ""1*"""7'..- 1-*:-- ***~~ :. * "11 ",/'; *r I '. I ~ I ,j" ~ ., l*I I ' ' *I 1'11.tl' 1 'I *;. 'H 'r11:1 11 ... * '* '1 *.
__ J
Exemption Valve Requested Remarks 12 SJ 29 No 13 SJ 29 No 14 SJ 29 No 1 SJ 3.0 Yes These valves are in their required positions with power removed from the valve operators in accordance with Technical Specification 4.5.2 and cannot be exercised during plant operation in accordance with IWV 3410(b) (1). Valves will be exercised during cold shutdown 1 SJ 31. No 1 SJ 32 No 11 SJ 33 No 12 SJ 33 No 11 SJ 34 No 12 SJ 34 No 11 SJ 39 No 12 SJ 39 No 11 SJ 40 Yes Sarne as 1 SJ 30 12 SJ 40 Yes Same as 1 SJ 30 11 SJ 43 No -I I
12 SJ 43 No 13 SJ 43 No 14 SJ 43. No 11 SJ 44 Yes Sarne as 1 SJ 30 12 SJ 44 Yes Same as 1 SJ 30
Valve Exempt *
e 11 SJ 45 No 12 SJ 45 No 11 SJ 48 No 12 SJ 48 No 11 SJ 49 No 12 SJ 49 No 1 SJ 53 No 11 SJ 54 Yes These valves are in their required positions with power removed from the valve operators in accordance with Technical Specification 4.5.1 and.cannot be exercised during
- , plant operation in accordance with IWV 3410 (b) (1)
- Valves will be exercised during cold shutdown.
12 SJ 54 Yes Sarne as 11 SJ 54 13 SJ 54 Yes Sarne as 11 SJ 54 14 SJ 54* Yes Sarne as 11 SJ 54 11 SJ 55 No 12 SJ 55 No 13 SJ 55 No 14 SJ 55 No 11 SJ 56 No 12 SJ 56 No 13 SJ 56 No 14 SJ 56 No 1 SJ 60 No 1 SJ 67 Yes Sarne as 1 SJ 30 1 SJ 68* Yes Sarne as 1 SJ 30 1 SJ 69 Yes Sarne as 1 SJ 30 1 SJ 70 No 1 SJ 71 No 11 SJ 93 *NO 12 SJ 93 No 13 SJ 93 No
Valve
'*1 Exemption Reguested Remarks 14 SJ 93 No 1 SJ 108 No 11 SJ 113 No 12 SJ 113 No 1, SJ 114 No 1 SJ 123 No 11 SJ 134 No 12 SJ 134 No 1 SJ 135 Yes Same as 1 SJ 30 13 SJ 139 No 14 SJ 139 No 11 SJ 144 No 12 SJ 144 No 13 SJ 144 No 14 SJ 144 No 1 SJ 150 No 11 SJ 156 No 12 *SJ 156 No 13 SJ 156 No 14 SJ 156 No 1 SJ 254 No Component Cooling System 11 CC 1 No 12 CC l No 13 CC 1 No
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e e Exemption Valve Requested Remarks 11 cc 15 No 12 cc 15 No 1 cc 68 No 1 cc 109 No l**cc 113 No 1 cc 117 No 1 cc :118 No 1 cc 131 No 1 cc 136 No 1 cc 137 No 1 cc 147 No 1 cc 187 No 1 cc 190 No 1 cc 215 No 1 cc 317 No 1 cc 320 No Chilled Water System 11 CH 13 No 12 CH 13 No 1 CH 30 No 1 CH 61 No 1 CH 74 No 1 CH 151 No 1 CH 168 No
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"i e Exemption Valve . Requested Remarks Residual Heat Removal System 1 RH 1 No 1 RH 2 No 1 RH 3 No ll**RH 4 No 12 RH 4 No 11 Ra 8 No 12 RH 8 No 11 RH 10 No 12 RH 10 No 11 RH 14 No 12 RH 14 No 11 RH 18 No 12 RH 18 No 11 RH 19 No 12 RH 19 No 1 RH 26 Yes Same as 1 SJ 30 13 RH. 27 No 14 RH 27 No.
Auxiliary Feedwater system 11 AF 4 No 12 AF 4 No 13 AF 4 No 11 AF 8 No 12 AF 8 No l.!. AF ,,
No 12 AF 11
- 13 AF 11 No
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- Exempti9n Valve Requested Remarks 14 AF 11 No 11 AF 21 No 12 AF 21 No 13 AF 21 No 14 AF 21 No 11 AF 23 No 12 AF 23 No 13 AF 23 No 14 AF 23 No 1 AF 104 No 1 AF 105 No 1 AF 106 No 1 AF 128 No Containment Spray System 11 cs 1 No 12 cs 1 No 11 cs 2 No 12 cs 2 No 11 cs 4 No 12 cs 4 No 11 cs 5 No 12 cs 5 No 11 cs 6 No 12 cs 6 No 1 cs 14 Yes Same as 1 SJ 30 1 cs 16 No 1 cs 17 No
'* 11 cs 20 No
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e Exemption Valve Requested Remarks 12 cs 20 No 11 I
cs 21 No 12 cs 21 No 1 cs 26 No 11 cs 36 No 12 cs 36 No 11 cs 48 No 12 cs 48 No Main Steam System 11 MS 7* No 12 MS 7 No 13 MS 7 No 14 MS 7 l. No 11 MS 10 No 12 MS 10 No 13 MS 10 No 14 MS 10 No 11 MS 11 *No 12 MS 11 No 13 MS 11 No 14 MS 11 No 11 MS 12 No 12 11.:lS 12 No 13 MS 12 No 14 MS 12 No l~o 11 MS 13 12 MS 13 No
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Exemption Valve Requested Remarks 13 MS 13 No 14 MS 13 No 11 MS 14 No*
12 MS 14 No 13 MS 14 No 14 MS 14 No 11 MS 15 No 12 MS 15 No 13 MS 15 No 14 MS 15 No l l MS 18 No 12 MS *19 No 13 MS 18 No 14 MS 18 No 1 MS 132 No 11 MS 167 Yes Cannot full-stroke valve during normal operation, nor* during cold shutdown.
yalves required steam to operate, therefore full
.stroking will be done during Mode 3 or 4 operation.
12 MS 167 Yes Same as 11 MS 167 13 MS 167 Yes Same as 11 MS 167 14 MS 167* Yes Same as 11 MS 167 11 MS 169 Yes ;(Dump valve for rapid closure of MSIV's). Valves are not accessible during normal operation. Exercis-ing to be done only during cold shutdown.
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.* Exemption Valve Requested Remarks 12 MS 169 Yes Same as 11 MS 169 13 MS 169 Yes Same as 11 MS 169 14 MS 169 Yes Same as 11 MS 169 11 MS 171 Yes Same as 11 MS 169 12 MS 171 Yes Same as 11 MS 169 13 MS 171 Yes. Same as 11 MS 169 14 MS 171 Yes Same as 11 MS 169 Fuel Oil System 11 DF 40 No 12 DF 40 No 11 DF 41 No 12 DF 41 No 11 DF 42 No 12 DF 42 No 11 DF 61 No 12 DF 61 No 11 DF 62 No 12 DF 62 No 11 DF 63 No 12 DF 63 No 11 DF 66 No 12 DF 66 No 13 DF 66 No
,* I ;* "i ' II I *; "',""' * ! ; ~ ' . ,**. '1 I" TI
e Exemption Valve Requested Remarks Reactor Coolant System 1 PS 1 No 1 PS 2 No 1 PS 3 No 1-PS 4 No 1 PR 1 No 1 PR 2 No 1 J?R 3 No 1 PR 4 No 1 PR 5 No 1 PR 6 No 1 PR 7 No 1 PR 17 No 1 PR 18 No 1 PR 25 No 1 NT 25 No 1 NT 26 No 1 WR 80 No 1 WR 81 No Chemical and Volume Control System 1 BR 78 No 1 BR 79 No 11 BR 81 No
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I Exemption Valve Requested Remarks 1 BR 99 No 11 BR 101 No 12 BR 101 No 13 BR 101 No 1 BR 113 No 11 BR 151 No 12 BR 151 No 13 BR 151 No 11 BR 152 No 12 BR 152 No 13 BR 152 No 1 CV 3 No 1 CV 4 No
.1 CV 5 No 1 CV 7 No 1 CV 21 No 1 CV 23 No 1 CV 27 No l- CV 35 No l CV 36 No l CV 40 No 1 CV 41. No 1 CV 42 No 1 CV 44 No 1 CV 47 No 1 CV 48 No 1 CV 49 No
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e e Exemption Valve Requested Remarks 1 CV 52 No 1 CV 53 No 1 CV 54 No 1 CV 55 No 1 CV 56 No 1 CV 57 No 1 CV 63 No 1 CV 64 No 1 CV 68 No 1 CV 69 No 1 CV 71 No 1 CV 74 No 1 CV 75 No 1 CV 77 No 1 CV 79 No 1 CV 81 No 1 CV 82 No 11 CV 98 No 12 CV 98 No 13 CV 98 No 14 CV 98 No 11 CV 99 No 12 CV 99 No 13 CV 99 No 14 CV 99 No 1 CV 114 No 1 CV 116 Nq 1 CV 124 No 1 CV 131 No 1 CV 132 No
e Exemption Valve Requested Remarks l CV 134 No l
I CV 135 No 1 CV 137 No 1 CV 139 No 1 CV 140 No 1 CV 147 No 11 CV 154 No 12 CV 154 No 11 CV 160 No 12 CV 160 No l CV 172 No 1 CV 173 No 1 CV 175 No 1 CV 176 No 1 CV 179 No 1 CV 180 No 1 CV 181 No 1 CV 183. No 1 CV 185 No 1 CV 189 No 1 CV 196 No 1 CV 198 No 1 CV 241 No 1 CV 253 No 1 CV 275 No 1 CV 277 No
.. . . . '*-*- *' -~-
e Exemption Valve Requested Remarks 1 CV 278 No 1 CV 284 No Service Water System
. 11 SW 1 No 12 SW 1 No 13 SW 1 No 14 SW 1 No 15 SW 1 No 16 SW 1 No 11 SW 2 'No 12 SW 2 No 13 SW 2 No
- 14. SW 2 No 15 SW 2 No 16 SW 2 No 11 SW 3 No 12 SW 3 No 13 SW 3 No 14 SW 3 No 15 SW 3 No 16 SW 3 No 11 SW 5 No 12 SW 5 .No 13 SW 5 No 14 SW 5 No 11 SW 6 No 12 SW 6 No 11 SW 8 No
. 12 SW 8 No 11 SW 9 No 12 SW 9 No 11 SW 10 No 12 SW 10 No 13 SW 10 No
- l4 SW 10 No 15 SW 10 No
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e Exemption Valve Requested Remarks 16 SW 10 No 11 SW 11 No 12 SW 11 No 13 SW 11 No 14 SW 11 No 15 SW 11 No 16 SW 11 No 11 SW 12 No 12 SW 12 No 13 SW 12 No 14 SW 12 No 15 SW 12 No 16 SW 12 No 11 SW 13 No 12 SW 13 No 13 SW 13 No 14 SW 13 No 15 SW 13 No*
16 SW 13 No 11 SW 15 No 12 SW 15 No 13 SW 15 No 14 SW 15 No 15 SW 15 No 16 SW 15 No 11 SW 17 No 12 SW 17 No 11 SW 20 No 12 SW 20 No 13 SW 20 No 14 SW 20 No I
11 SW 21 No 12 SW 21 No 11 SW 22 No 12 SW 22 No
\.
Valve Requested Remarks 11 SW 23 No 12 SW 23 No 11 SW 24 No 12 SW 24 No 13 SW 24 No 14 SW 24 No 15 SW 24 No 16 SW 24 No 1 SW 26 No 1 SW 29 No 11 SW 34 No 12 SW 34 No 11 SW 36 No 12 SW 36 No 11 SW 38 No 12 SW 38 No 11 SW 39. No 12 SW 39 No 13 SW 39 No 11 SW 42 Nb 12 SW 42 No 13 SW 42 No 11 SW 44 No 12 SW 44 No 13 SW 44 No 11 SW 47 No 12 SW 47 No
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- Exemption Valve Reguested Remarks 11 SW 49 Yes Valve is pressure controlled and does not
Cannot full-stroke exercise this valve.
12 SW 49 Yes Same as 11 SW 49 11 SW 51 No 12 SW 51 No 11 SW 52 No 12 SW 52 No 11 SW 53 No 12 SW 53 No 11 SW 57 Yes The SW 57 valves and the corresponding SW 58 valves operate from a single actuator. There is a common position indicator for each pair of valves.
Operation of the valves cannot be physically observed. Therefore, stroke time cannot be determined.
12 SW 57 Yes Same as 11 SW 57 13 SW 57 Yes Same as 11 SW 57 14 SW 57 Yes Sarne as 11 SW 57 15 SW 57 Yes Same as 11 SW 57 11 SW 58 Yes Same as 11 SW 57 12 *SW 58 Yes Same as 11 SW 57 13 SW 58 Yes Same as 11 SW 57 14 SW 58 Yes Same as 11 SW 57 15 SW 58 Yes Same as 11 SW 57 11 SW 72 No 12 SW 72 No 13 SW 72 No 14 SW 72 No 15 SW 72 No 11 SW 77 No 12 SW 77 No 11 SW 78 No 12 SW 78 No 11 SW 79 No 12 SW 79 No
Valve
'*i
- Exemption Requested Remarks
-.1 SW 81 No 1 SW 89 No.
11 SW 90 No 12 SW 90 No 11 SW 92 No 12 SW 92 No 13 SW 92 No 11 SW 99 No 12 SW 99 No.
13 SW 99 No 1 SW 104 No 1 SW 105 Yes Valve is pressure controlled and does not have manual actuator.
Cannot full-stroke exercise this valve.
l SW 107 Yes valve is temperature controlled and does not have manual actuator.
Cannot full-stroke exercise this valve.
11 SW 122 No 12 SW 122 No 11 SW 127 No 12 SW 127 No 11 SW 129 No 12 SW 129 No 11 SW 134 No 12 SW 13.4 No 1 SW 137 No 1 SW 142 No 11 SW 145 No 12 SW 145 No 11 SW 150 No 12 SW 150 No 11 SW 153 No
' No 12 SW 153 11 SW 158 No 12 SW 158 No
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- Exemption Valve Requested Remarks 1 SW 163 No*
1 SW 168 No 1 SW 169 No 1 SW 175 No 1 SW 180 No 1 SW 185 No 1 SW 191" No 1 SW 196 No 1 SW 199 No 1 SW 204 No 1 SW 205 No 1 SW 210 No 1 SW 213 No 11 SW 223 Yes Valve is pressure controlled and does not have manual actuator.
Cannot full-stroke exercise this valve.
12 SW 223 Yes Same as 11 SW 223 13 SW 223 Yes Same as 11 SW 223 14 SW 223 Yes Same as 11 SW 223 15 SW 223 Yes Same as 11 SW 223 1 SW 913 No 1 SW 914 No 1 SW 915. No 1 SW 917 No 1 SW 918 No 1 SW 919 No 1 SW 920 No 1 SW 921 No Liquid Radwaste System 1 WL 12 No 1 WL 13 No l WL, 16 No 1 WL 17 No 1 WL 96 No 1 WL 97 No
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Valve
- Exemption Requested Remarks 1 WL 98 No 1 WL 99 No 1 WL 108 No 1 WL 190 No 1 WL 191 No Sampling System 1 SS 27 No 1 SS 33 No 1 SS 49 No 1 SS 64 No 11 SS 93 No 13 SS 93 No 14 SS 93 No 11 SS 94 No 12 SS 94 No
-13 SS 94 No 14 SS 94 No 1 SS 103 No 1 SS 104 No 1 SS 107 No 1 SS 110 No Main Feedwater System 11 BF 19 No 12 BF 19 No 13 BF 19 No 14 BF 19 No 11 BF 40 No 12 BF 40 No 13 BF 40 No 14 BF 40 No