|
---|
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] Category:Technical Specifications
MONTHYEARML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML21050A0022021-03-12012 March 2021 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21047A3132021-03-10010 March 2021 Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary) ML20281A6132020-11-0909 November 2020 Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling ML20231A6322020-09-29029 September 2020 Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17047A0202017-03-21021 March 2017 Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML17053A1782017-03-15015 March 2017 Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 ML15141A2712015-06-17017 June 2015 and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses ML14108A3992014-12-18018 December 2014 Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual 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 ML14108A3122014-07-29029 July 2014 Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual 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-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual2013-07-30030 July 2013 License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual 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-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012 Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process ML0527202982011-07-20020 July 2011 Current Facility Operating License NPF-57, Tech Specs, Revised 12/18/2017 ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal ML1109801512011-04-19019 April 2011 Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425 LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 1872011-04-0404 April 2011 Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187 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-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010 Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. ML1015907132010-07-21021 July 2010 Issuance of Amendment Control Rod Notch Testing Frequency LR-N10-0097, License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension2010-03-29029 March 2010 License Amendment Request: Emergency Diesel Generators a and B Allowed Outage Time Extension LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2010-03-19019 March 2010 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML0932700232009-12-0808 December 2009 Issuance of Amendment Mode Change Limitations ML0934302422009-12-0101 December 2009 License Amendment Request to Adopt TSTF-460, Revision 0, Control Rod Scram Times. ML0916006832009-07-15015 July 2009 Issuance of Amendment Technical Specification Requirements Related to Snubbers LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications2009-01-0505 January 2009 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications LR-N08-0150, Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request2008-07-30030 July 2008 Relief Request for Third Interval Inservice Inspection Program for Examinations and Tests of Snubbers and Associated License Amendment Request LR-N08-0071, License Amendment Request - Hydrogen Water Chemistry Low Power Restriction2008-04-25025 April 2008 License Amendment Request - Hydrogen Water Chemistry Low Power Restriction ML0734500402008-01-24024 January 2008 Tech Spec Pages for Amendment 173 Control Room Habitability LR-N08-0003, Supplement to License Amendment Request for Extended Power Uprate2008-01-16016 January 2008 Supplement to License Amendment Request for Extended Power Uprate ML0728500372007-10-16016 October 2007 Technical Specifications, Issuance of Amendment Removal of Turbine First Stage Pressure Values from Technical Specifications ML0724003042007-08-27027 August 2007 Tech Spec Pages for Amendment 171 Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications LR-N07-0215, Supplement to License Amendment Request for Extended Power Uprate2007-08-27027 August 2007 Supplement to License Amendment Request for Extended Power Uprate ML0724805722007-06-15015 June 2007 Gnf S-0000-0068-2643, Gnf Additional Information Regarding the Requested Changes to the Technical Specification Slmcpr. Hope Creek (KT1) Cycle 15 LR-N07-0061, Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-17017 April 2007 Application to Revise Technical Specifications (LCR H07-01) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0630704822006-10-31031 October 2006 Tech Spec Pages for Amendment 170 Regarding Clarification of Requirements During Handling of Irradiated Fuel Core Alterations, and Operations with the Potential for Draining the Reactor Vessel ML0624101882006-08-28028 August 2006 Technical Specifications - Fuel Storage and Handling ML0621403972006-08-0101 August 2006 Technical Specifications, Issuance of Amendment Ultimate Heat Sink, MC8054 LR-N06-0259, Supplement to Request for License Amendment Ultimate Heat Sink2006-07-18018 July 2006 Supplement to Request for License Amendment Ultimate Heat Sink ML0610105472006-04-10010 April 2006 Technical Specifications Pages Re Relocation of the Component Identification from the Overcurrent Protective Device Lists in TS 3/4.8.4.1, Primary Containment Penetration Conductor Overcurrent Protective Devices, and TS 3/4.8.4.5 2024-01-16
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 kPP*- -*
0 .PSEG NuclearLLC APR 2.5 2008 10 CFR 50.90 LR-N08-0071 LAR H08-01 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
License Amendment Request - Hydrogen Water Chemistry Low Power Restriction In accordance with the provisions of IOCFR50.90, PSEG Nuclear LLC (PSEG) hereby requests an amendment of the Technical Specifications (TS) for the Hope Creek Generating Station (HCGS). In accordance with 10CFR5O.91(b)(1), a copy of this submittal has been sent to the State of New Jersey.
PSEG proposes to revise the requirements for operation of the HCGS Hydrogen Water Chemistry (HWC) system; to remove restrictions on operation of the system at low power while maintaining required Main Steamline Radiation Monitor (MSLRM) functions. This change will permit operation of HWC at low power levels thereby increasing the time that it is in service.
The current TS restrictions (footnotes in TS Section 3/4.3.2, Isolation Actuation Instrumentation) limit placing HWC in service until reactor power reaches 20% of rated thermal power. The footnotes also permit increasing the MSLRM setpoints above 20% of rated thermal power to accommodate an expected increase in main steamline radiation with HWC in service.
The original restriction on HWC injection was intended to prevent increases in main steamline radiation background before the MSLRM setpoints were adjusted because it was assumed that the main steamline radiation would increase significantly with HWC operation. However, the present HWC injection rate does not cause an appreciable increase in main steamline radiation; therefore, the reason for prohibiting HWC operation below 20% no longer exists. In addition, coD
/o s' 95-2168 REV. 7199
Document Control Desk Page 2 LR-N08-0071 the HWC system is a non-safety related balance of plant system that does not meet any of the 10 CFR, 50.36 criteria for inclusion in the TS. The removal of HWC system from TS is consistent with Standard Technical Specifications (STS) for General Electric Plants (BWR/4), Rev. 3 (NUREG-1433). provides the existing TS pages marked-up to show the proposed changes.
PSEG has evaluated the proposed changes in accordance with IOCFR50.91(a)(1),
using the criteria in ICFR50.92(c), and has determined this request involves no significant hazards considerations. This amendment to the Hope Creek TS meets the criteria of 10CFR51.22(c)(9) for categorical exclusion from an environmental impact statement.
PSEG requests approval of the proposed License Amendment by March 31, 2009, to be implemented within 30 days, to support Hope Creek Refueling Outage 15.
If you have any questions or require additional information, please do not hesitate to contact Mr. Jeff Keenan at (856) 339-5429.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on /*5/2*0?
(Date)
Sincerely, George P. Barnes Site Vice President, Hope Creek Generating Station Attachments (2)
S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
Attachment I LAR H08-01 LR-N08-0071 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS Hydrogen Water Chemistry Low Power Restriction Table of Contents
- 1. DE S C R IP T IO N .............................................................................................. .. 2
- 2. PR O PO S ED C HA NG E .................................................................................... 2
- 3. BA C KG R O UND ............................................................................................... .. 3
- 4. TEC HNICA L A NA LY S IS .................................................................................. 4
- 5. REGULATORY SAFETY ANALYSIS .............................................................. 5
- 6. ENVIRONMENTAL CONSIDERATION ........................................................... 10
- 7. R E F E R E NC E S ............................................................................................. 10
Attachment I LAR H08-01 LR-N08-0071
1.0 DESCRIPTION
PSEG Nuclear LLC (PSEG) proposes to revise the requirements for operation of the Hydrogen Water Chemistry (HWC) system at the Hope Creek Generating Station (HCGS); to remove restrictions on operation of the system at low power while maintaining required Main Steamline Radiation Monitor (MSLRM) functions. This change will permit operation of HWC at low power levels thereby increasing the time that it is in service.
The present HCGS Technical Specifications (TS) contains restrictions on the operation of the HWC system in the form of footnotes in TS Section 3/4.3.2, LCO 3.3.2, Isolation Actuation Instrumentation, Main Steamline Radiation Monitor (MSLRM), function and setpoint. Specifically, TS 3/4.3.2 Table 3.3.2-1 Trip Function 3.b Applicable Operating Condition contains footnote ## and 3/4.3.3.2 Table 3.3.2-2 Trip Function 3.b contains footnote ###. Both footnotes limit placing HWC in service until reactor power reaches 20% of rated thermal power. The footnotes also permit increasing the MSLRM setpoints above 20% of rated thermal power to accommodate an expected increase in main steamline radiation with HWC in service.
The proposed change would revise these footnotes to remove the restriction on HWC operation below 20% rated thermal power while retaining the MSLRM setpoint change provisions.
The original restriction on HWC injection was intended to prevent increases in main steamline radiation background before the MSLRM setpoints were adjusted because it was assumed that the main steamline radiation would increase significantly with HWC.
operation. However, the present HWC injection rate does not cause an appreciable increase in main steamline radiation; therefore, the reason for prohibiting HWC operation below 20% no longer exists. In addition, the HWC system is a non-safety related balance of plant system that does not meet any of the 10 CFR 50.36 criteria for inclusion in the TS. The removal of HWC system from TS is consistent with Standard Technical Specifications (STS) for General Electric Plants (BWR/4), Rev. 3 (NUREG-1433).
2.0 PROPOSED CHANGE
Current TS 3/4.3.2, LCO 3.3.2, Table 3.3.2-1 Trip Function 3.b Applicable Operating Condition footnote ##, and TS 3/4.3.3.2 Table 3.3.2-2 Trip Function 3.b footnote ###,
will be revised as follows:
The hydrogen water- Ghemictry (HI4WO) system shagl not be placed in seA4Gie unti r.. e.tO power reahe*s Below 20% of RATED THERMAL POWER, the Main Steamline Radiation Monitor setpoints shall not exceed the values determined using normal full power background radiationlevels with the hydrogen water chemistry (HWC) system shut down. After reaching 20% of RATED THERMAL POWER,-an p4rio* to operaing the HW*C system, the normal full power background radiation level 2
Attachment I LAR H08-01 LR-NO8-0071 and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection. Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC system has been shut off, the background level and associated setpoint shall be returned to the normal full power values. If the Main Steamline Radiation Monitor setpoints have been increasedfor HWC operation and a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.
In addition to the above proposed change, one clarification to the current location of footnote ## on page 3/4 3-12 (Table 3.3.2-1 Trip Function 3.b) is being proposed.
Currently the mode applicability is indicated as:
1,2, 3##
This could be interpreted to be applicable to Modes 1, 2 and 3, or to just Mode 3.
PSEG Nuclear is requesting a clarification to the mode applicability as follows:
1 ##, 2##, 3 The power restrictions of HWC only apply to power operation and startup modes (Modes 1 and 2). provides the existing TS pages marked-up to show the proposed changes.
3.0 BACKGROUND
The HWC system injects hydrogen into the primary coolant system to reduce Intergranular Stress Corrosion Cracking (IGSCC). The original system required hydrogen flow rates that caused significant increases in main steamline radiation. The TS was amended (Amendment 8) to permit use of HWC on a test basis. Amendment 23 made permanent TS changes for HWC operation. The TS restricted HWC operation until after 20% of rated thermal power, and permitted increasing the MSLRM isolation setpoint from 3 times normal full power background to 3 times the full power background measured with HWC in service. The MSLRM is credited with mitigating the consequences of a Control Rod Drop Accident (CRDA) that is of concern only below 10% power. An increase in setpoint would reduce the sensitivity of the MSLRM to fuel failures resulting from a CRDA. Therefore, increasing the MSLRM setpoints was permitted only above 20% of rated thermal power where a control rod drop was analyzed not to create fuel failures. The Electric Power Research Institute (EPRI) provided the basis for the original HWC system design (Reference 7.1). The NRC accepted this analysis in Amendments 8 and 23.
Amendment 53 removed the MSLRM scram and MSIV closure functions, and HCGS subsequently modified the plant to remove these functions. Amendment 53 did not, however, remove the function to trip the Mechanical Vacuum Pumps (MVP). The 3
Attachment I LAR H08-01 LR-N08-0071 HCGS CRDA Analysis still credits MVP trip. Amendment 143 added specific testing requirements for the MVP trip function to TS 3/4.3.10.
In 2007, HCGS implemented the General Electric NobleChemTM application (Reference 7.7). This allowed the HWC hydrogen injection rate to be reduced significantly from 35 scfm to approximately 9 scfm at full power. The resulting main steamline radiation background, at full power, was only approximately 8% higher than the non-HWC full power background. The HWC hydrogen injection rate is increased proportionally to power level; flow rates are lower at lower power levels.
EPRI has developed recommendations for improvements to HWC system availability and IGSCC protection (Reference 7.2). One of these enhancements is to begin operation of the system at approximately 5% of rated thermal power. PSEG wishes to implement this recommendation at HCGS; with HWC operation commencing when at least one secondary condensate pump and a Steam Jet Air Enjector (SJAE) are in service (approximately 5% of rated thermal power). The technical justification is discussed in Section 4.0.
HCGS has submitted a License Amendment Request to implement a Constant Pressure Power Uprate (Reference 7.6). Implementation of the power uprate is expected to require an increase in HWC hydrogen flow rate but without significant increase in main steamline radiation background at full power with HWC in service. The power uprate will have no adverse impact on operation of HWC at low power.
The removal of HWC system from TS is consistent with Standard Technical Specifications (STS) for General Electric Plants (BWR/4), Rev. 3 (NUREG-1433). The HWC system is a non-safety related balance of plant system that does not meet any of the 10 CFR 50.36 criteria for inclusion in the TS; this is evaluated in Section 5.2.
4.0 TECHNICAL ANALYSIS
The Isolation Actuation system at HCGS uses the MSLRM to trip the two MVPs and isolate the Reactor Water Sample lines via valves SV-431 0, Inboard Containment Isolation Valve (Recirc Loop Sampling) and SV-431 1 1, Outboard Containment Isolation Valve (Recirc Loop Sampling), (Reference 7.4). The MVP trip is credited in the CRDA Analysis (Reference 7.3). The MVPs are secured prior to exceeding 5% of rated thermal power as required by plant procedures (Reference 7.5). The sample line isolations are not credited in the CRDA Analysis.
The TS footnotes (described in Sections 1.0 and 2.0 above) were intended to provide a means to safely increase the MSLRM setpoints to permit operation of the HWC system at higher main steamline radiation background levels. The MSLRM setpoints without HWC injection are assumed in the CRDA and must be maintained below 20% of rated thermal power. The original restriction on HWC injection was intended to prevent 1 The GE nomenclature for these valves is B31-F019 and B31-F020, respectively.
4
Attachment I LAR H08-01 LR-N08-0071 increases in main steamline radiation background before the MSLRM setpoints were adjusted because it was assumed that the main steamline radiation would increase significantly at low power. Reference 7.1, Section 8.2, discusses the reasons for a dual MSLRM setpoint and concluded that increases in setpoint above 20% power can be justified independent of HWC. Since the present HWC injection rate does not cause an appreciable increase in main steamline radiation (as discussed in Section 3.0 above),
the reason for prohibiting HWC operation below 20% no longer exists. The required MSLRM setpoints below 20% will not be impacted by operation of HWC at low power.
The proposed changes would remove the limitation on HWC operation below 20%
power and maintain the controls on the MSLRM setpoint, still permitting setpoint increases above 20% of rated thermal power if required to operate HWC. Future increases in the MSLRM setpoints are not anticipated but this provides flexibility should the need arise.
Reference 7.2 and 7.8 evaluated HWC injection at low power conditions and concluded that it was feasible and beneficial to IGSCC prevention. Several operating BWR plants have already implemented this change, including LaSalle and Cooper. The implementation of low power HWC operation will follow the guidelines in BWRVIP-156 (Reference 7.2) to ensure reliable operation of the HWC system. Low power operation of HWC will be controlled by Plant procedures.
In addition to the above analyzed change, one clarification to the current location of footnote ## on page 3/4 3-12 (Table 3.3.2-1 Trip Function 3.b) is being proposed.
Currently the mode applicability is indicated as:
1,2, 3##
This could be interpreted to be applicable to Modes 1, 2 and 3, or to just Mode 3.
Neither of these interpretations is accurate. PSEG Nuclear is requesting a clarification to the mode applicability as follows:
1 ##, 2##, 3 Clarifying that the power restrictions of HWC only apply to power operation and startup modes (Modes 1 and 2) is acceptable because the MVP trip function for the CRDA is only applicable in Modes 1 and 2 (reference TS Bases 3/4.3.10).
5.0 Regulatory Safety Analysis 5.1 Basis for proposed no significant hazards consideration determination As required by 10CFR50.91 (a), PSEG provides its analysis of the no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
5 LAR H08-01 LR-N08-0071
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3. Involve a significant reduction in a margin of safety.
The determinations that the criteria set forth in 10CFR50.92 are met for this amendment request are indicated below:
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
Hope Creek Generating Station (HCGS) proposes to amend Technical Specification (TS) 3/4.3.2 to remove a limitation on operation of the Hydrogen Water Chemistry (HWC) System below 20% of rated thermal power. The original HWC system injected hydrogen into the condensate system at levels that caused significant increases in the main steamline radiation background. As a consequence, it was necessary to also increase the Main Steamline Radiation Monitor (MSLRM) setpoints to prevent undesirable MSLRM alarms and reactor water sample line isolations. However, the MSLRM is credited with mitigating the consequences of a Control Rod Drop Accident (CRDA) that is of concern only below 10% power. An increase in setpoint would reduce the sensitivity of the MSLRM to fuel failures resulting from a CRDA. Therefore, increasing the MSLRM setpoints is permitted only above 20% of rated thermal power where a control rod drop was analyzed not to create fuel failures. As a result of a revised system application, the HWC injection rate is now much lower than that applied originally, and main steamline radiation does not increase significantly when HWC is placed in service. Consequently there is no impact on the MSLRM setpoints at low power (below 20%).
HWC injection itself is not associated with any accident or operational occurrence analyzed in the Updated Final Safety Analysis Report (UFSAR). The purpose of HWC is to reduce Intergranular Stress Corrosion Cracking (IGSCC) in the reactor coolant system. IGSCC can lead to a loss of coolant accident. Lowering the power level at which HWC injection is initiated will increase the time that hydrogen is injected and improve IGSCC prevention. Low power operation is recommended, by EPRI, to increase the time that HWC is in service. EPRI has evaluated HWC operation on plant safety systems and concluded that there are no adverse effects associated with HWC injection at low power. The implementation of low power HWC operation will follow the guidelines in BWRVIP-156 (Reference 7.2) to ensure reliable operation of the HWC system.
The Control Rod Drop Accident (CRDA) is the only accident applicable to the MSLRM isolation actuation 'function. This accident can result in fuel failures if it 6
Attachment I LAR H08-01 LR-N08-0071 occurs below 10% of rated thermal power but is not of concern above 10%
power. The MSLRM trips the two Mechanical Vacuum Pumps (MVP) and isolates reactor water sample lines on high main steamline radiation. The MSLRM is credited with fuel failure detection and MVP trips in the CRDA Analysis. The MVPs are secured prior to reaching 5% of rated thermal power.
The proposed change does not alter the present TS requirement prohibiting MSLRM setpoint increases below 20% of rated thermal power and thereby does not change the plant response assumed in the CRDA Analysis.
In conclusion, the proposed change will not significantly increase the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated.
Response: No.
The HWC injects hydrogen into the secondary condensate pump suction lines and injects oxygen into the Offgas system. The existing TS prohibits HWC operation at power levels below 20% of rated thermal power. The proposed change would permit HWC at any power level. Operating procedures would begin the HWC injection at approximately 5% power when sufficient condensate flow is available to transport the hydrogen in the reactor coolant system. Injection of hydrogen into the reactor coolant system has proven to be beneficial to the reactor vessel and recirculation system piping components. The implementation of low power HWC operation will follow the guidelines in BWRVIP-156 (Reference 7.2) to ensure reliable operation of the HWC system. The TS requirements for the MSLRM Isolation Actuation functions will remain unchanged. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the change involve a significant reduction in a margin of safety?
Response: No.
The safety margin applicable to this change is the MSLRM setpoint to main steamline radiation assumed in the CRDA Analysis. The MSLRM trip of the MVPs is credited in the CRDA Analysis. The MSLRM setpoint requirements are not changed by this proposed license amendment; both the existing and proposed footnotes associated with the MSLRM Isolation Actuation TS permit increasing the MSLRM setpoints only if the plant is operated above 20% of thermal power. This is outside the power range at which the CRDA is of concern. There is no other safety margin associated with operation of HWC.
Therefore, there is no reduction in the margin of safety.
7
Attachment I LAR H08-01 LR-NO8-0071 5.2 Applicable Regulatory Requirements/Criteria 10CFR20.1(c) and Regiulatory Guide 8.8 - Potential for increases in main steamline radiation is addressed in 10CFR20.1(c) and Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be as low as Reasonably Achievable (ALARA)". The present and planned future operation of HWC results in lower main steamline radiation levels and lower occupational radiation exposure.
EPRI NP-5283-SR - A - Hydrogen and Oxygen storage issues are addressed in EPRI NP-5283-SR-A, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations - 1987 Revision. The proposed amendment does not impact the HWC system compliance with these requirements Branch Technical Position CMEB 9.5-1 and NUREG -0800, Section 9.5.1 Standard Review Plan - Hydrogen storage issues in relation to fire protection are addressed in these regulatory documents. The proposed amendment does not impact the HWC system compliance with these regulatory requirements.
10 CFR 50.36 - 10 CFR 50.36 specifies the criteria for limiting conditions for operation (LCOs) in the TS for commercial power reactors. An LCO must be established for items that meet one or more of the following four criteria:
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant degradation of the reactor coolant pressure boundary.
The HWC system does not involve control room instrumentation that is used to detect a significant degradation of the reactor coolant pressure boundary. The HWC system is a non-safety related balance of plant system; the sole function of the system is to inject hydrogen into the primary coolant system to reduce pipe IGSCC.
Therefore, the HWC elements of TS 3/4.3.2 Table 3.3.2-1 footnote ##, and Table 3.3.2-2 footnote ###, do not fall within or satisfy this criterion.
Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The HWC system does not involve a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis.
The HWC system is a non-safety related balance of plant system. The MSLRM setpoints without HWC injection, which are assumed in the CRDA and must be maintained below 20% of rated thermal power, are not changed by removal of the HWC low power restriction from TS. Therefore, the HWC elements of TS 3/4.3.2 Table 3.3.2-1 footnote ##, and Table 3.3.2-2 footnote ###, do not fall within or satisfy this criterion.
8
Attachment I LAR H08-01 LR-N08-0071 Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The HWC system is a non-safety related balance of plant system that has no function in mitigating a design basis accident or transient. The HWC system injects hydrogen into the primary coolant system solely to reduce IGSCC. The MSLRM setpoints without HWC injection, which are assumed in the CRDA and must be maintained below 20% of rated thermal power, are not changed by removal of the HWC low power restriction from TS. Therefore, the HWC elements of TS 3/4.3.2 Table 3.3.2-1 footnote ##, and Table 3.3.2-2 footnote ###, do not fall within or satisfy this criterion.
Criterion 4: A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The HWC system is a non-safety related balance of plant system; the removal of the restriction on operation of the HWC system at low power is not significant to public health and safety. The MSLRM setpoints without HWC injection, which are assumed in the CRDA and must be maintained below 20% of rated thermal power, are not changed by removal of the HWC low power restriction from TS. Therefore, the HWC elements of TS 3/4.3.2 Table 3.3.2-1 footnote ##, and Table 3.3.2-2 footnote ###, do not fall within or satisfy this criterion.
The above evaluation demonstrates that the TS Table notes for HWC do not fall within or satisfy the 10 CFR 50.36 criteria for retention in the TS.
5.3 Conclusion Removal of the HWC system low power operation TS restriction involves no significant hazards consideration and is consistent with 10 CFR 50.36. 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.
9
Attachment I LAR H08-01 LR-N08-0071
6.0 ENVIRONMENTAL CONSIDERATION
In accordance with 10 CFR 51.22(b), an evaluation of this license amendment request has been performed to determine whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) of the regulations.
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 10CFR20.
However, 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 effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9).
Therefore, pursuant to 1 OCFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
7.1 EPRI NP-5283-SR-A, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations - 1987 Revision 7.2 EPRI 1011706, BWRVIP-156: BWR Vessel and Internals Project 7.3 UFSAR Section 15.4.9 Control Rod Drop Accident 7.4 UFSAR Section 7.3.1.1.2 Primary Containment and Reactor Vessel Isolation Control Systems 7.5 Procedure HC.OP-SO.CG-0001 CONDENSER AIR REMOVAL OPERATION 7.6 PSEG Letter LR-N06-0286, Request for License Amendment: Extended Power Uprate, September 18, 2006.
7.7 Design Change Package (DCP) 80029363, which issued VTD 325206, "Noble Metal Chemical Addition Technical Safety Evaluation," GE Doc # GE-NE-0000-0042-2228-02-R1.
7.8 GE-NE-0000-0052-0721-01-RO, Feasibility Report, Hope Creek Generating Station HWCI System Low Power Operation and Air Injection 10 LAR H08-01 LR-N08-0071 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating No. NPF-57 are affected by this license amendment request:
Technical Specification Page TS 3/4.3.3.2 Table 3.3.2-1 3/4 3-12 TS 3/4.3.3.2 Table 3.3.2-1 3/4 3-16a TS 3/4.3.3.2 Table 3.3.2-2 3/4 3-25
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION VALVE ACTUA-TION GROUPS MINIMUM APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL PER TRIP SYSTEM(a) CONDITION ACTION
- 3. MAIN STEAM LINE ISOLATION
- a. Reactor Vessel Water Level - 1 2 1, 2, 3 21 Low Low Low, Level 1
- b. Main Steam Line Radiation - 2 (b) 2 M##, 2##, 344 28 High, High
- c. Main Steam Line Pressure - 2 1 22 Low 1
- d. Main Steam Line Flow - High 2/line 1, 2, 3 20 1
- e. Condenser Vacuum - Low 2 1, 2**, 3** 21 1
- f. Main Steam Line Tunnel 2/line 1, 2, 3 21 Temperature - High
- g. Manual Initiation 1, 2, 17 2 1, 2, 3 25
- 4. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. RWCU A Flow - High 7 1/Valve (e) 1, 2, 3 23
- b. RWCU A Flow - High, Timer 7 1/Valve (e) 1, 2, 3 23
- c. RWCU Area Temperature - High 7 6/Valve (e) 1, 2, 3 23
- d. RWCU Area Ventilation A 7 6/Valve (e) 1, 2, 3 23 Temperature-High
- e. SLCS Initiation 7cf) 1/Valve le) 1, 2 23
- f. Reactor Vessel Water 7 2/Valve (e) I, 2, 3 23 Level - Low Low, Level 2
- g. Manual Initiation 7 1/Va lve Ce) 1, 2, 3 25 HOPE CREEK 3/4 3-12 Amendment No. 4-7--
TABLE 3.3.2-1 (Continued)
NOTES
- When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.
Th...e .
lhyd.r.gen wat-er eie...try (HW) .....
y.t.. ll net be placed in scervice until r.eeter. p.werr* eahe Below 20% of RATED THERMAL POWER the Main Steamline Radiation Monitor setpoints shall not exceed the values determined using normal full power-background radiation levels with the hydrogen water chemistry (HWC) system shut down. After reaching 20% of RATED THERMAL POWER, prior
.en. ..
te epereting the H..C systefim, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection. Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC
...ten be b.een shu.t.eff, the background level and associated setpoint shall be returned to the normal full power values. If the Main Steamline Radiation Monitor setpoints have been -increasedfor HWC operation and a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.
(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b) Also trips and isolates the mechanical vacuum pumps.
(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).
(d) DELETED (e) Sensors arranged per valve group, not per trip system.
(f) Closes only RWCU system isolation valve(s) HV-F001 and HV-F004.
)g) Requires system steam supply pressure-low coincident with drywell pressure-high to close turbine exhaust vacuum breaker valves.
)h) Manual isolation closes HV-F008 only, and only following manual or automatic initiation of the RCIC system.
(i) Manual isolation closes HV-F003 and HV-F042 only, and only following manual or automatic initiation of the HPCI system.
(j) Trip functions common to RPS instrumentation.
HOPE CREEK 3/4 3-16a Amendment No. 4 TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE
- 7. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION
- a. Reactor Vessel Water Level -
Low, Level 3 Ž!12.5 inches* Ž 11.0 inches
- b. Reactor Vessel (RHR Cut-in Permissive) Pressure - High Ž 82.0 psig Ž 102.0 psig
- c. Manual Initiation NA NA
- See Base's Figure B 3/4 3-1.
- These setpoints are as follows:
160°F- RWCU pipe chase room 4402 140°F - RWCU pump room and heat exchanger rooms 1350F - RWCU pipe chase room 4505
- 30 minute time delay.
- 15 minute time delay.
- The bydregen w.t.er .hemitr y (HWC)
.. syst. shall nt be pi.e.e. in serviee until
. eatr.
.ce.he.
p.wer.
Below 20% of RATED THERMAL POWER the Main Steamline Radiation Monitor setpoints shall not exceed the values determined using normal full power background radiation levels with the hydrogen water chemistry (HWC) system shut down. After reaching 20% of RATED THERMAL POWER, and pr-io to ope.ating t*he HW s...ste-, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection. Prior to decreasing below 20% of RATED THERMAL POWER and .fferthe HWC system has been shutoff the background level and associated setpoint shall be returned to the normal full power values. If the Main Steamline Radiation Monitor setpoints have been increased for HWC operation and a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.
HOPE CREEK 3/4 3-25 Amendment No. 3-1