Similar Documents at Salem |
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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 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
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN 2 8 2006 LR-N06-0276 LCR S05-08 NuclearLLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENT TO LCR S05-08: REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS, CONTAINMENT ISOLATION VALVES SALEM GENERATING STATION, UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10 CFR 50.90, PSEG Nuclear LLC (PSEG) previously submitted, on September 26, 2005, License Change Request (LCR) S05-08 requesting an amendment of the Technical Specifications (TS) for Salem Generating Station, Unit Nos. 1 and 2. This submittal supplements'the September 26, 2005 submittal, providing clarifying information based on discussions with the NRC Staff.
Pursuant to the requirements of 10 CFR 50.91 (b)(1), a copy of this request for amendment supplement has been sent to the State of New Jersey.
LCR S05-08 proposed eliminating the Surveillance Requirement (SR) for containment isolation valves (Salem Unit I SR 4.6.3.1.1 and Salem Unit 2 SR 4.6.3.1) that are being returned to service after maintenance, repair or replacement work to be consistent with the requirements in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants." This proposed change will minimize unnecessary testing and plant transients while continuing to assure that the necessary quality of systems and components is maintained.
In Section 3, "Background" of Attachment I to LCR S05-08, a discussion was provided on post-maintenance testing after valve stem packing adjustments and backseating of valves. The purpose of this discussion was to provide one example of maintenance on a valve that would not adversely affect valve performance parameters, and would therefore not need to be subjected to the SR requirements; post-maintenance testing would ensure that the equipment meets all applicable SRs before restoring the equipment to operable status. It was further stated in Section 3 that:
"The effect of Salem Unit I SR 4.6.3.1.1 and Salem Unit 2 SR 4.6.3.1 is to require valve stroke testing after repairs, such as valve packing adjustments, even when it can be demonstrated that the repairs would not adversely affect valve performance parameters."
95-2168 REV. 7/99
.1 #-'
Document Control Desk UN~2 8 2006 LR-N06-0276 The discussion of valve packing adjustments was not meant to be exclusive; it was meant as an example of any maintenance, repair, or replacement work that is performed on the valve or its associated actuator, control, or power circuit that would not adversely affect valve performance parameters. The deletion of the SR requirement will provide flexibility in determining the appropriate post-maintenance test based on the work performed, and that when appropriate, a timed valve stroke test will be performed to ensure component operability following maintenance activities.
This change is consistent with Westinghouse Standard Technical Specifications (STS);
STS SR 3.6.3.5, verification of isolation time of containment isolation valves, is strictly a periodic surveillance, there is no reference to the conduct of maintenance.. A similar TS amendment was provided to Millstone Unit 3 via Amendment 200 dated December 21, 2001.
Ifyou have any questions concerning this request, please contact Mr. Jamie Mallon at (610) 765-5507.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on /,/`./ " Sincerely, v/ (DOae)
Thomas P. Joyc Site Vice President Salem Generating Station
Document Control Desk LR-N06-0276 .UN 2 8 2006 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. S. Bailey, Project Manager - Salem Unit I and Unit 2 Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem Unit 1 and Unit 2 (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625