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Category:Letter type:LR
MONTHYEARLR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves 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-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle 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 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-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges LR-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-N23-0035, 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-N23-0010, 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-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) 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-N22-0019, 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-N22-0016, 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-N22-0011, 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-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes 2024-08-06
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARLR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves ML24142A4292024-05-20020 May 2024 Enclosures 1, 3, 4, 5, 6 and 7: Hope Creek Technical Specification Conversion to NUREG-1433, Rev. 5 ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle 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-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 2024-06-28
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 MAR 2 9 2002 0 PSEG NuclearLLC LR-N02-0039 LCR H02-04 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Gentlemen:
REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS EXTENDED USE OF PRESSURE - TEMPERATURE LIMIT CURVES HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Pursuant to 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests a revision to the Technical Specifications for the Hope Creek Generating Station. In accordance with 10CFR50.91 (b)(1), a copy of this submittal has been sent to the State of New Jersey.
The proposed amendment will allow the use of the pressure-temperature curves approved in Amendment 131 for an additional cycle until revised curves are submitted utilizing Regulatory Guide 1.190 methodology as part of Hope Creek's extended power uprate. The submittal of Technical Specification changes for the extended power uprate are targeted for May 2003 to be implemented in the Fall 2004 outage (end of Cycle 12).
PSEG has evaluated the proposed changes in accordance with 10CFR50.91(a)(1),
using the criteria in 10CFR50.92(c), and has determined this request involves no significant hazards considerations. The proposed amendment also meets the eligibility criteria for categorical exclusion set forth in 1 OCFR51.22(c)(9). An evaluation of the requested changes is provided in Attachment 1 to this letter. The marked up Technical Specification pages affected by the proposed changes are provided in Attachment 2.
PSEG requests approval of the proposed License Amendment by February 1, 2003 to be implemented within 60 days. This will allow startup from Hope Creek's eleventh (11) refueling outage which is scheduled in April 2003.
95-2168 REV. 7/99
Document Control Desk MAR 2 9 2002 LR-N02-0039 Below is a summary of the commitments made in this submittal:
o Based upon approval of this request, new pressure-temperature limit curves will be submitted as part of the Hope Creek extended power uprate utilizing the methodology of Regulatory Guide 1.190. Submittal of the technical specification changes are targeted for May 2003 with implementation of the extended power uprate in the Fall 2004 outage.
Should you have any questions regarding this request, please contact Mr. Brian Thomas at 856-339-2022.
Sincerely, David F. Garchcw(
Vice President - Operations Attachments (2)
C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission ATTN: Mr. R. Ennis, Licensing Project Manager - Hope Creek Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - HC (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
Document Control Desk MAR 2 9 2002 LR-N02-0039 I declare under penalty of perjury that the foregoing is true correct.
Executed on Q. - -
-i Vice - Operations
Document Control Desk LR-N02-0039 LCR H02-04 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 EVALUATION OF REVISIONS TO THE TECHNICAL SPECIFICATIONS FOR EXTENDED USE OF PRESSURE-TEMPERATURE LIMIT CURVES
Document Control Desk LR-N02-0039 Attachment I LCR H02-04 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS EXTENDED USE OF PRESSURE-TEMPERATURE LIMIT CURVES Table of Contents
- 1. DES C R IP T IO N ..................................................................................................... 1
- 2. PR O PO S E D C HA NG E ......................................................................................... 1
- 3. BA C KG R O UND ............................................................................................... 1
- 4. TECHNICAL ANALYSIS .................................................................................. 2
- 5. REGULATORY SAFETY ANALYSIS ............................................................... 3 5.1 No Significant Hazards Consideration .................................................... 3 5.2 Applicable Regulatory Requirements/Criteria ......................................... 4
- 6. ENVIRONMENTAL CONSIDERATION ............................................................ 5
- 7. R E FE R E NC E S ................................................................................................. 5
Document Control Desk LR-N02-0039 LCR H02-04 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS EXTENDED USE OF PRESSURE-TEMPERATURE LIMIT CURVES
- 1. DESCRIPTION The proposed amendment would revise the Hope Creek Technical Specifications contained in Appendix A to the Operating License to extend the use of the current pressure-temperature through the end of Cycle 12 operation. In Amendment 131 issued July 30, 2001 to increase the licensed power level by approximately 1.4%, the NRC approved the revision of the reactor vessel pressure-temperature (P-T) limits through the end of Cycle 11, which is currently scheduled to end in April 2003.
- 2. PROPOSED CHANGE The proposed changes to the Technical Specifications would revise the footnote on Figure 3.4.6.1-1, "Hydrostatic Pressure and Leak Tests Pressure/Temperature Limits- Curve A," Figure 3.4.6.1-2, "Non-Nuclear and Cooldown Pressure/Temperature Limits - Curve B," and Figure 3.4.6.1-3, "Core Critical Heatup and Cooldown Pressure/Temperature Limits - Curve C." The current footnote states, "This figure is valid through Cycle 11 Operation in accordance with NRC Safety Evaluation supporting Amendment No. 131." The revised footnote will read, "This figure is valid through Cycle 12 Operation in accordance with NRC Safety Evaluation supporting Amendment No. __"
For consistency purposes, the note on figures 3.4.6.1-1, 3.4.6.1-2 and 3.4.6.1-3 which states that the, "Curves are valid for 32 EFPY of operation" is being deleted.
The marked up Technical Specification pages are included in Attachment 2.
- 3. BACKGROUND On July 30, 2001, the NRC approved Amendment 131 to the Hope Creek Technical Specifications to allow an increase in licensed power level to 3339 MWt. As part of this amendment, PSEG requested changes to the pressure temperature (P-T) limits for the Hope Creek reactor vessel. In the Safety Evaluation Report (SER) supporting Amendment 131 the NRC noted that the P-T limit curves were developed with an applicability of 32 effective full power years (EFPY) of operation which corresponds to the end of the current license.
In a teleconference between the NRC Staff and PSEG, the staff indicated that there were unresolved technical issues regarding the methodology used to derive the fluence values for the amendment. Specifically, the revised P-T curves did not reflect the guidance contained in Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Page 1 of 5
Document Control Desk LR-N02-0039 Attachment I LCR H02-04 Fluence," (subsequently issued as Regulatory Guide 1.190 in March 2001).
Therefore the P-T curves could not be approved for the entire operation of 32 EFPY.
As an interim solution, PSEG requested in Reference 2 to add a note to the P-T limit curves to allow their use until the end of Cycle 11. Prior to the end of Cycle 11 PSEG would resubmit new P-T limit curves utilizing the guidance of Regulatory Guide 1.190.
Following approval of Amendment 131 on July 30, 2001, PSEG determined that it will be performing an extended power uprate of Hope Creek. The extended power uprate is currently scheduled to be implemented in the Fall of 2004 at the conclusion of the end of Cycle 12 operation. As a result of the extended power uprate, the Hope Creek Technical Specifications will need to be revised including the pressure-temperature limit curves discussed above to reflect the increase in rated thermal power. As a result of this decision, PSEG is requesting that the current P-T limit curves approved in Amendment 131 for use until the end of cycle 11 be extended for use until the end of cycle 12. The P-T curves that will be submitted as part of the extended power uprate for Hope Creek will be performed utilizing the methodology of Regulatory Guide 1.190.
- 4. TECHNICAL ANALYSIS The proposed amendment would revise the note associated with Figures 3.4.6.1 1, 3.4.6.1-2 and 3.4.6.1-3 to extend the use of the P-T limit curves for an additional cycle.
As stated above, the P-T limit curves approved in Amendment 131 did not reflect the guidance contained in Draft Regulatory Guide DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence,"
(subsequently issued as Regulatory Guide 1.190 in March 2001). Therefore the P-T curves could not be approved for the entire operation of 32 EFPY.
The maximum fluence used to develop the current P-T limit curves is 5.24 x 1017 n/cm 2 . For the same rated power level, fluence is directly proportional to EFPY.
The maximum fluence above relates to 32 EFPY which is assumed to be at the end of the plant license (2026). In previous discussions, the NRC had indicated that the new Regulatory Guide (RG) 1.190 methods could result in fluence that is approximately 20% higher than the previous methods. In evaluating the feasibility of extending the current P-T limit curves to the end of cycle 12, an assumption was used that the actual fluence value would be 50% higher than the current values. This means that the fluence at 32 EFPY would be 1.5 times higher than was assumed in the existing P-T limits. Using this assumption, the maximum fluence value of 5.24 x 1017 n/cm 2 would be reached at 21.3 EFPY (32/1.5). Thus for a 50% higher fluence, the current P-T limit curves would be valid to 21.3 EFPY.
Page 2 of 5
Document Control Desk LR-N02-0039 Attachment I LCR H02-04 At the end of the previous cycle (cycle 10) in October 2001, the EFPY of operation was 12.2 EFPY. Utilizing fuel design projections, Hope Creek would reach 21.3 EFPY in fuel cycle 17, which is projected to start in year 2010.
Therefore with a 50% higher fluence value, the current P-T curves would still be valid until the year 2010. Based on the above, the currently approved P-T curves would provide more than sufficient margin to operate until the end of cycle 12 (Fall 2004) and ensure that the reactor vessel integrity is protected under all operating conditions.
For consistency purposes, the note on figures 3.4.6.1-1, 3.4.6.1-2 and 3.4.6.1-3 which states that the, "Curves are valid for 32 EFPY of operation" is being deleted. Removal of this note will eliminate any confusion associated with the note that will state that the curves are only valid to the end of cycle 12.
- 5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration PSEG Nuclear LLC (PSEG) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment" as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment to revise the technical specifications to extend the use of the pressure-temperature (P-T) limits does not affect the operation or configuration of any plant equipment. Thus, no new accident initiators are created by this change. The proposed change extends the use of the P-T limits for an additional cycle. The P-T limits are based on the projected reactor vessel neutron fluence at 32 effective full power years (EFPY) of operation. At the end of cycle 10, Hope Creek Generating Station (HCGS) was at approximately 12.2 EFPY of operation (38.1% of the 32 EFPY). At the end of cycle 12 there will remain sufficient margin to ensure that the current 32 EFPY fluence projections will not be exceeded. This ensures that the basis for proposed applicability of the current P-T limits is conservative for use until the end of cycle 12 ensuring that the reactor vessel integrity is protected under all operating conditions.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Page 3 of 5
Document Control Desk LR-N02-0039 Attachment I LCR H02-04
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment revises the technical specifications to extend the use of the pressure-temperature (P-T) limits. It does not change the design function or operation of any systems, structures or components.
Plant operation will not be affected by the proposed amendments and no new failure mechanisms, malfunctions or accident initiators will be created. The current P-T limits will remain valid and conservative during the proposed extension period.
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 change involve a significant reduction in a margin of safety?
Response: No.
The proposed change extends the use of the current P-T limits for an additional cycle of operation. The P-T limits are based on the projected reactor vessel neutron fluence at 32 EFPY of operation. At the end of cycle 10 in April 2000, HCGS was at approximately 12.2 EFPY of operation (38.1% of the 32 EFPY). At the end of cycle 12, HCGS will have obtained less than 50% of the 32 EFPY operating time which provides significant margin to ensure that the current 32 EFPY fluence projection will not be exceeded. This ensures that the basis for the P-T limits is conservative for use through the end of cycle 12 and therefore ensures that the reactor pressure vessel integrity is protected under all operating conditions.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, PSEG concludes that the proposed changes present 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.
5.2 Applicable Regulatory Requirements/Criteria Appendix G to 10 CFR Part 50 specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary to provide adequate margins of safety during any condition of Page 4 of 5
Document Control Desk LR-N02-0039 Attachment I LCR H02-04 normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected to over its service lifetime. Appendix G requires that certain pressure-temperature (P-T) limits for reactor pressure vessels must be at least as conservative as limits obtained by following the methods of analysis and the margins of safety of Appendix G to Section Xl of the ASME Code.
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.
- 6. ENVIRONMENTAL CONSIDERATION PSEG has determined the proposed amendment 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 a surveillance requirement. The proposed amendment 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 amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed change is not required.
- 7. REFERENCES
- 1. PSEG Nuclear letter LR-NOO-0405 from Mark B. Bezilla to Document Control Desk "Request for License Amendment Increased Licensed Power Level," dated December 1, 2000.
- 2. PSEG Nuclear Letter LRN-01-0052 from Mark B. Bezilla to Document Control Desk, "Supplemental Information for Request for License Amendment Increased Licensed Power Level," dated February 12, 2001.
- 3. NRC Amendment 131, "Hope Creek Generating Station, Issuance of Amendment RE: 1.4% Increase in Licensed Power Level," dated July 30, 2001.
- 4. Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," March 2001.
Page 5 of 5
Document Control Desk LR-N02-0039 LCR H02-04 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this change request:
Technical Specification Page Figure 3.4.6.1-1 3/4 4-23 Figure 3.4.6.1-2 3/4 4-23a Figure 3.4.6.1-3 3/4 4-23b
Figure 3.4.6.1-1 Hydrostatic Pressure and Leak Tests PressurelTemperature Limits - Curve A 1,200 1,100 All system leakage and hydrostatic (0
pressure tests performed during the S1,000 service life of the pressure boundary
< in compliance with ASME Code "U 900 Section XI a.
0 ~r's ie 'lidfor of U-1EFP I- 800
.J
'U U,
U) 700
'U oI 600 "LU 500 z
t: 400 LU 300 LU 200 - Beitline Boltup 100 79*F U+H - - - Bottom Head
- - Upper Vessel 0
0 50 100 150 200 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F)
Note: This figure is valid through Cycle 14 12 Operation in accordance with NRC Safety Evaluation Report supporting Amendment No. __
HOPE CREEK 3/4 4-23 Amendment No. 434-
Figure 3.4.6.1-2 Non-Nuclear Heatup and Cooldown Pressure/Temperature Limits - Curve B 1,200
_ 1,100 0.
CL 1,000 All heatup and cooldowns that 0
uIJ are performed when the reactor "x 900 is not critical at the normal
(. heatup and cooldown rate of 0
100Flhr
..J 800 LU U) Q',. . .,"lid for 2 =FPv of (4 700 LU O 600 lU
<C LU 500 z
- 400 LU 300 rC,
- Beitline u,, 200 W)
LU
- a. - - - Bottom Head UU I BoltupjI Iuu
- -Upper Vessel 0-0 50 100 150 200 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)
Note: This figure is valid through Cycle 14 12 Operation with NRC Safety Evaluation Report supporting Amendment No.
HOPE CREEK 3/4 4-23a Amendment No. 4-3 Figure 3.4.6.1-3 Core Critical Heatup and Cooldown Pressure/Temperature Limits - Curve C 1,200 S1,100 All heatup and cooldowns that are C. performed when the reactor is critical at r' 1,000 the normal heatup and cooldown rate of 0
w 100 Flhr Z 900
- 0. QI'
.. ..... d.f.r 32
... P.
0 800 W
o I 600 Lu 500 W
z
- 400 LU "300 normal water level 88°F Cn 200 Lu SMinimum criticality with
(. 100 0
0 50 100 150 200 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)
Note: This figure is valid through Cycle 44 12 Operation in accordance with NRC Safety Evaluation Report supporting Amendment No.
HOPE CREEK 3/4 4-23b Amendment No. 1-3-1-