Similar Documents at Salem |
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Category:Letter type:LR
MONTHYEARLR-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) 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 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 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-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) 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 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 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 LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities 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 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 2024-07-24
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 MAY 02 2007 PSEG Nuclear LLC LR-N07-0098 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Salem Generating Station, Units 1 and 2 Facility Operating License Nos. DRP-70 and DRP-75 NRC Docket Nos. 50-272 and 50-311
Subject:
2006 Summary Of Revised Regulatory Commitments In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG Nuclear LLC (PSEG) submits this correspondence to discuss commitments that were changed and not reported by other means during 2006.
Salem Unit I And 2 Reactor Pressure Vessel Bottom Mounted Instrument Nozzle Penetration Visual Inspection Frequency In response to NRC Bulletin 2003-02, PSEG committed to performing bare metal visual (BMV) examinations of the reactor pressure vessel (RPV) bottom mounted instrument (BMI) penetrations during every refueling outage. Subsequently, PSEG performed the BMV examinations of the RPV BMI penetrations during the Salem Unit 1 Refueling Outages' 1R16 and 1R17, and Salem Unit 2 Refueling Outages' 2R13 and 2R14 with no evidence of leakage identified.
With satisfactory inspection results from two consecutive refueling outages in each Salem unit and a review of inspection frequencies at other PWR facilities (Reference NUREG -1863, Review of Responses to NRC Bulletin 2003-02 Leakage from Reactor Pressure Vessel Lower Head Penetrationsand Reactor Coolant PressureBoundary Integrity) and striving to significantly reduce ALARA exposure goals, PSEG revised the original commitment to perform bare metal visual examinations of the RPV BMI penetrations from every refueling outage to every other refueling outage. It is noted that this 'every other outage' inspection frequency is consistent with a pending ASME Code Case N-722, Additional Examinationsfor PWR PressureRetaining Welds in Class I Components FabricatedWith Alloy 600/82/182 Materials, and will significantly reduce in exposure.
95-2168 REV. 7/99
MAY 0 2 2D Document Control Desk Page 2 LR-N07-0098 The next bare metal visual examinations of the RPV BMI penetrations will be 1 R1 9 (Fall 2008) for Salem Unit I and 2R16 (Spring 2008) for Salem Unit 2.
If you have any questions or require additional information, please contact Howard Berrick at 856-339-1862.
Sincerely, Thomas P. Joyce Site Vice President - Salem C Mr. S. Collins Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Salem and Hope Creek Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 MAY 02 2007 PSEG Nuclear LLC LR-N07-0098 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Salem Generating Station, Units 1 and 2 Facility Operating License Nos. DRP-70 and DRP-75 NRC Docket Nos. 50-272 and 50-311
Subject:
2006 Summary Of Revised Regulatory Commitments In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG Nuclear LLC (PSEG) submits this correspondence to discuss commitments that were changed and not reported by other means during 2006.
Salem Unit I And 2 Reactor Pressure Vessel Bottom Mounted Instrument Nozzle Penetration Visual Inspection Frequency In response to NRC Bulletin 2003-02, PSEG committed to performing bare metal visual (BMV) examinations of the reactor pressure vessel (RPV) bottom mounted instrument (BMI) penetrations during every refueling outage. Subsequently, PSEG performed the BMV examinations of the RPV BMI penetrations during the Salem Unit 1 Refueling Outages' 1R16 and 1R17, and Salem Unit 2 Refueling Outages' 2R13 and 2R14 with no evidence of leakage identified.
With satisfactory inspection results from two consecutive refueling outages in each Salem unit and a review of inspection frequencies at other PWR facilities (Reference NUREG -1863, Review of Responses to NRC Bulletin 2003-02 Leakage from Reactor Pressure Vessel Lower Head Penetrationsand Reactor Coolant PressureBoundary Integrity) and striving to significantly reduce ALARA exposure goals, PSEG revised the original commitment to perform bare metal visual examinations of the RPV BMI penetrations from every refueling outage to every other refueling outage. It is noted that this 'every other outage' inspection frequency is consistent with a pending ASME Code Case N-722, Additional Examinationsfor PWR PressureRetaining Welds in Class I Components FabricatedWith Alloy 600/82/182 Materials, and will significantly reduce in exposure.
95-2168 REV. 7/99
MAY 0 2 2D Document Control Desk Page 2 LR-N07-0098 The next bare metal visual examinations of the RPV BMI penetrations will be 1 R1 9 (Fall 2008) for Salem Unit I and 2R16 (Spring 2008) for Salem Unit 2.
If you have any questions or require additional information, please contact Howard Berrick at 856-339-1862.
Sincerely, Thomas P. Joyce Site Vice President - Salem C Mr. S. Collins Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Salem and Hope Creek Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625