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Category:Letter type:LR
MONTHYEARLR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0034, 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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes 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-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges 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-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage 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-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 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-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022 2022 Annual 10 CFR 50.46 Report LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate 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-N22-0041, 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-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums 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-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022 Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs 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-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021 Corrected Hope Creek 10 CFR 50.46 Reports 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-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021 2021 Annual 10 CFR 50.46 Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021 Emergency Plan Document Revisions Implemented August 10, 2021 LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021 In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021 Correction to Prior Spent Fuel Cask Registration Letter LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021 Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021 Deviation from EPRI Document 33002012244 Inspection Requirements LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication 2023-09-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARLR-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 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes 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-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements LR-N20-0051, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2020-07-21021 July 2020 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors LR-N19-0076, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-11-25025 November 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors LR-N19-0064, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer2019-07-29029 July 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer LR-N19-0065, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements2019-07-0808 July 2019 License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements LR-N19-0060, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-18018 June 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program LR-N19-0038, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2019-04-22022 April 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR LR-N19-0004, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2019-04-18018 April 2019 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0098, License Amendment Request: Remote Shutdown System2018-10-30030 October 2018 License Amendment Request: Remote Shutdown System LR-N18-0086, Supplemental Information to License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or 82018-09-26026 September 2018 Supplemental Information to License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or 8 LR-N18-0059, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2018-06-29029 June 2018 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules LR-N18-0032, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension2018-04-13013 April 2018 License Amendment Request: Inverter Allowed Outage Time (AOT) Extension LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0032, License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-03-27027 March 2017 License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report LR-N17-0060, Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2017-03-27027 March 2017 Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. LR-N16-0175, License Amendment Request - Administrative Controls2016-10-17017 October 2016 License Amendment Request - Administrative Controls LR-N16-0156, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-0707 October 2016 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-N16-0103, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using Consolidated Line Item Improvement Process2016-07-20020 July 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using Consolidated Line Item Improvement Process LR-N16-0066, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-06-17017 June 2016 License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N16-0092, Supplemental Information - License Amendment Request - Digital Power Range Neutron Monitoring (Prnm) System Upgrade2016-06-17017 June 2016 Supplemental Information - License Amendment Request - Digital Power Range Neutron Monitoring (Prnm) System Upgrade ML16181A1932016-06-0808 June 2016 Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change LR-N16-0099, Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2016-06-0808 June 2016 Hope Creek Generating Station License Amendment Request - Safety Limit Minimum Critical Power Ratio Change LR-N16-0002, License Amendment Request to Amend Technical Specifications (TS) to Delete Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves (Srvs)2016-05-11011 May 2016 License Amendment Request to Amend Technical Specifications (TS) to Delete Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves (Srvs) ML15265A2242015-09-21021 September 2015 License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade2015-09-21021 September 2015 Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0147, License Renewal Commitment Implementation2015-07-22022 July 2015 License Renewal Commitment Implementation LR-N14-0224, License Amendment Request to Update Appendix B to the Renewed Facility Operating License2014-12-0909 December 2014 License Amendment Request to Update Appendix B to the Renewed Facility Operating License LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process LR-N13-0265, License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule2013-12-24024 December 2013 License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N12-0200, for License Amendment Request - Cyber Security Plan Implementation Schedule Milestones2012-07-26026 July 2012 for License Amendment Request - Cyber Security Plan Implementation Schedule Milestones LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012 License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0343, License Amendment Request - Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out-of-Service2010-09-22022 September 2010 License Amendment Request - Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out-of-Service ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1021500732010-07-20020 July 2010 License Amendment Request H09-02 to Relocate the Reactor Recirculation System Motor-Generator (MG) Set Scoop Tune Stop Setting Surveillance ML1021500922010-07-20020 July 2010 License Amendment Requests H10-02 & S10-02: Proposed Revision to Technical Specifications - Removal of Reactor Coolant System Structural Integrity Requirements. 2023-09-08
[Table view] |
Text
PSEG Nuclear U.C P. 0. Box 236, Hancocks Bridge, New Jersey 08038-0236 OPSEG
\'t td ear LLC 10 CFR 50.90 LR-N19-0060 LAR H19-03 JUN 1 8 2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Application to Revise Technical Specifications to Adopt TSTF-563, "Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program" In accordance with the provisions of 10 CFR 50.90, PSEG Nuclear LLC (PSEG) is submitting a request for an amendment to the Technical Specifications (TS) for Hope Creek Generating Station (Hope Creek).
PSEG requests adoption of TSTF-563, "Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program." TSTF-563 revises the Technical Specification (TS) definitions of Channel Calibration and Channel Functional Test, which currently permit performance by means of any series of sequential, overlapping, or total channel steps, to allow the required frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program. provides a description and assessment of the proposed changes. provides the existing TS pages marked to show the proposed changes. provides revised (clean) TS pages.
Approval of the proposed amendment is requested within one year of submittal acceptance. Once approved, the amendment shall be implemented within 60 days.
In accordance with 10 CFR 50.91, a copy of this application is being provided to the designated State of New Jersey Official.
There are no regulatory commitments contained in this letter.
J 1 8 LR-N19-0060 10 CFR 50.90 Page 2 If you have any questions or require additional information, please contact Mr. Lee Marabella at 856-339-1208.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ----
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Respectfully,
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C Eric Carr Site Vice President Hope Creek Generating Station : Description and Assessment : Proposed Technical Specification Changes (Mark-Up) : Revised Technical Specification Pages cc: Administrator, Region I, NRC NRC Project Manager, Hope Creek NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE PSEG Corporate Commitment Tracking Coordinator Hope Creek Commitment Tracking Coordinator
LR-N19-0060 LAR H19-03 Attachment 1 Description and Assessment Page 1
LR-N19-0060 LAR H19-03
1.0 DESCRIPTION
PSEG Nuclear LLC (PSEG) requests adoption of TSTF-563, "Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. " TSTF-563 revises the Technical Specification (TS) definitions of Channel Calibration and Channel Functional Test, which currently permit performance by means of any series of sequential, overlapping, or total channel steps, to allow the required frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program.
- 2. 0 ASSESSMENT
- 2. 1 Applicability of Safety Evaluation PSEG has reviewed the safety evaluation for TSTF-563 provided to the Technical Specifications Task Force in a letter dated December 4, 2018. This review included a review of the NRC staff's evaluation, as well as the information provided in TSTF-563.
As described herein, PSEG has concluded that the justifications presented in TSTF-563 and the safety evaluation prepared by the NRC staff are applicable to Hope Creek and justify this amendment for the incorporation of the changes to the Hope Creek TS.
A Surveillance Frequency Control Program was incorporated into the Hope Creek TS in a license amendment dated February 25, 2011 (NRC Agency Documents Access and Management System (ADAMS) Accession No. ML103410243) as corrected in a license amendment supplement dated April 19, 2011 (ADAMS Accession No. ML110980151).
- 2. 2 Optional Changes and Variations PSEG is proposing the following variations from the TS changes described in the TSTF-563 or the applicable parts of the NRC staff's safety evaluation.
a) The Hope Creek TS utilize different numbering than the Standard Technical Specifications (STS) on which TSTF-563 was based. Specifically, definitions in the Hope Creek TS are in Section 1 vice Section 1. 1 and the definitions are numbered.
These differences are administrative and do not affect the applicability of TSTF-563 to the Hope Creek TS.
b) The Hope Creek TS are different from Revision 4 of the General Electric BWR/4 STS (NUREG-1433) on which TSTF-563 is based. The definition of Channel Calibration has wording differences from the STS definition that do not change the intent. The Hope Creek TS Channel Calibration definition states, "The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated. " The STS states, "The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps. " Elimination of the phrase "so that the entire channel is calibrated" in the proposed change has no effect because the definition previously states that the Channel Calibration must encompass the entire channel; therefore, the proposed change aligns the wording with that of the STS and Page 2
LR-N19-0060 LAR H19-03 is addressed in the technical justification of TSTF-563 which states in Section 3. 0 Technical Evaluation, "The proposed change to permit changing the surveillance frequency of channel component(s) does not affect the test method or evaluation method. The requirement to perform a channel calibration, channel functional test . . .
o n the entire channel i s not changed".
c) The Hope Creek definition of Channel Functional Test has wording differences from the STS definition that do not change the intent. The Hope Creek TS Channel Calibration definition states, "The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested." The STS states, "The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps." Elimination of the phrase "such that the entire channel is tested" in the proposed change aligns the wording with that of the STS and is addressed in the technical justification of TSTF-563 which states in Section 3.0 Technical Evaluation, "The proposed change to permit changing the surveillance frequency of channel component(s) does not affect the test method or evaluation method. The requirement to perform a channel calibration, channel functional test . . . on the entire channel is not changed. "
- 3. 0 REGULATORY ANALYSIS
- 3. 1 No Significant Hazards Consideration Analysis PSEG Nuclear LLC (PSEG) requests adoption of TSTF-563, "Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program." TSTF-563 revises the Technical Specification (TS) definitions of Channel Calibration and Channel Functional Test which currently permit performance by means of any series of sequential, overlapping, or total channel steps. Both definitions are revised to allow the required frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program.
PSEG has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment, " as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change revises the TS definitions of Channel Calibration and Channel Functional Test to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program. All components in the channel continue to be calibrated and tested. The frequency at which a channel is tested or calibrated is not an initiator of any accident previously evaluated, so the probability of an accident is not affected by the proposed change. The channels surveilled in Page 3
LR-N19-0060 LAR H19-03 accordance with the affected definitions continue to be required to be operable and the acceptance criteria of the surveillances are unchanged. As a result, any mitigating functions assumed in the accident analysis will continue to be performed.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change revises the TS definitions of Channel Calibration and Channel Functional Test to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program. All components in the channel continue to be calibrated and tested. The design function or operation of the components involved are not affected and there is no physical alteration of the plant (i. e., no new or different type of equipment will be installed). No credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases are introduced. The changes do not alter assumptions made in the safety analysis. The proposed changes are consistent with the safety analysis assumptions.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No The proposed change revises the TS definitions of Channel Calibration and Channel Functional Test to allow the frequency for testing the components or devices in each step to be determined in accordance with the TS Surveillance Frequency Control Program. All components in the channel continue to be calibrated and tested. The Surveillance Frequency Control Program assures sufficient safety margins are maintained, and that design, operation, surveillance methods, and acceptance criteria specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plants' licensing basis. The proposed change does not adversely affect existing plant safety margins, or the reliability of the equipment assumed to operate in the safety analysis. As such, there are no changes being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed change. Margins of safety are unaffected by method of determining surveillance test intervals under an NRC-approved licensee-controlled program.
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LR-N19-0060 LAR H19-03 Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, PSEG concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
- 3. 2 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
- 4. 0 ENVIRONMENTAL EVALUATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR
- 51. 22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
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LR-N19-0060 LAR H19-03 Enclosure 1 Proposed Technical Specification Changes (Mark-Up)
1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
1.2 DELETED AVERAGE PLANAR LINEAR HEAT GENERATION RATE 1.3 The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (A PLHGR} shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at that height.
CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHA NNEL C ALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD} or thermocouple sensors may consist of an inplace qualitative assessmemt of sensor behavior and normal calibration of the remaining adjustable devices in the channel.
The CHANNEL C ALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps eo that the entire ehannel is ealihrated , and each step must be performed within the Frequency in the Surveillance Frequenc Control Pro ram for the devices included in the step.
CHANNE E 1.5 A GHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONA L TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip function:3 and channel failure trips.
- b. Bistable channels - the injection of a simulated signal into the sensor to veify OPERABILITY including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps sae that the entire ehannel is tested., and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
HOPE CREEK 1-1 Amendment No.
LR-N19-0060 LAR H19-03 Enclosure 2 Revised Technical Specification Pages
1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved.
The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
1.2 DELETED AVERAGE PLANAR LINEAR HEAT GENERATION RATE 1.3 The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at that height.
CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
HOPE CREEK 1-1 Amendment No.xxx