Letter Sequence Response to RAI |
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CAC:MF9930, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi Project stage: Request ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) Project stage: Request ML17188A2602017-07-0707 July 2017 License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request LR-N17-0044, Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings2017-07-0707 July 2017 Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings Project stage: Other ML17222A1182017-08-16016 August 2017 Acceptance of Requested Licensing Action License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML17235B1202017-08-28028 August 2017 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N17-0141, Transmittal of 2017 Annual 10 CFR 50.46 Report2017-09-27027 September 2017 Transmittal of 2017 Annual 10 CFR 50.46 Report Project stage: Request ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb Project stage: RAI LR-N17-0161, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-0101 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML17324A0522017-11-0909 November 2017 NRR E-mail Capture - Draft Request for Additional Information - Hope Creek Mur Chemical, Corrosion, and Steam Generator Project stage: Draft RAI ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls Project stage: RAI ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate Project stage: RAI LR-N17-0170, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-27027 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0176, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate2017-12-14014 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate Project stage: Response to RAI LR-N17-0186, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0175, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0187, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0181, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0189, Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-22022 December 2017 Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML18011A0352018-01-11011 January 2018 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station (CAC No. MF9930; EPID L-2017-LLA-0426) Project stage: Withholding Request Acceptance LR-N18-0009, Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2018-01-22022 January 2018 Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Supplement ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) Project stage: Approval 2017-12-19
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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-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 2024-08-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARLR-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-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-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-N21-0018, 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 LR-N20-0069, Response to Final Request for Additional Information Regarding Revise Technical Specifications Requirements for High Pressure Coolant Injection System Inoperability2020-11-0404 November 2020 Response to Final Request for Additional Information Regarding Revise Technical Specifications Requirements for High Pressure Coolant Injection System Inoperability LR-N20-0043, PSEG Nuclear LLC - Response to Request for Additional Information, Adopt 10 CFR 50.69 LAR2020-06-25025 June 2020 PSEG Nuclear LLC - Response to Request for Additional Information, Adopt 10 CFR 50.69 LAR ML19308A5952019-11-0404 November 2019 Response to Request for Additional Information, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements ML19280A0002019-10-0303 October 2019 NRR E-mail Capture - Hope Creek, Salem 1 and 2 - Final RAI Emergency Plan Staffing Requirements (L-2019-LLA-0145) LR-N18-0109, Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension2018-10-17017 October 2018 Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension LR-N18-0107, Response to Request for Additional Information, License Amendment Request Inverter Allowed Outage Time (AOT) Extension (Electrical Branch)2018-10-17017 October 2018 Response to Request for Additional Information, License Amendment Request Inverter Allowed Outage Time (AOT) Extension (Electrical Branch) LR-N18-0073, Supplement to License Amendment Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-07-19019 July 2018 Supplement to License Amendment Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. LR-N18-0061, Response to Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-06-27027 June 2018 Response to Request for Additional Information, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. LR-N17-0189, Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-22022 December 2017 Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0175, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0187, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0181, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0186, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0176, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate2017-12-14014 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate LR-N17-0170, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-27027 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0161, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-0101 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0126, Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application2017-09-0505 September 2017 Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application LR-N17-0125, Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2017-08-11011 August 2017 Response to Request for Additional Information Regarding Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors LR-N17-0109, Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies2017-07-13013 July 2017 Response to Final Request for Additional Information (Rai), Permanently Extend Type a and Type C Leak Rate Test Frequencies LR-N17-0063, Response to Request for Additional Information, Permanently Extend Type a and Type C Leak Rate Test Frequencies2017-03-27027 March 2017 Response to Request for Additional Information, Permanently Extend Type a and Type C Leak Rate Test Frequencies LR-N16-0231, Response to Request for Additional Information, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-12-27027 December 2016 Response to Request for Additional Information, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N16-0226, Response to Request for Additional Information, Regarding Removing Certain Training Requirements2016-12-19019 December 2016 Response to Request for Additional Information, Regarding Removing Certain Training Requirements LR-N16-0232, Response to Prelim White Finding in Integrated Inspection Report 05000354/20160032016-12-14014 December 2016 Response to Prelim White Finding in Integrated Inspection Report 05000354/2016003 LR-N16-0192, Response to Request for Additional Information Stuck Open Safety/Relief Valves2016-12-13013 December 2016 Response to Request for Additional Information Stuck Open Safety/Relief Valves ML16305A2382016-10-31031 October 2016 Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spend Fuel Pools LR-N16-0165, Transmittal of Response to Request for Additional Information Regarding Digital Power Range Neutron Monitoring (Prnm) System Upgrade2016-09-23023 September 2016 Transmittal of Response to Request for Additional Information Regarding Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N16-0174, Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval2016-09-23023 September 2016 Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval LR-N16-0148, Supplemental Information Regarding Request for Relaxation from the Hardened Containment Vent Release Point Height Requirement of NRC Order EA-13-1092016-09-0707 September 2016 Supplemental Information Regarding Request for Relaxation from the Hardened Containment Vent Release Point Height Requirement of NRC Order EA-13-109 LR-N16-0137, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External2016-08-24024 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External LR-N16-0119, Response to Request for Additional Information Regarding Review of Post-Extended Power Uprate Steam Dryer Stress Calculation Acoustic Circuit Model Software Error2016-06-29029 June 2016 Response to Request for Additional Information Regarding Review of Post-Extended Power Uprate Steam Dryer Stress Calculation Acoustic Circuit Model Software Error LR-N16-0109, and Hope Creek Generating Stations - Cover Letter for Response to Request for Additional Information Regarding Review of Security Plan, Revision 172016-06-15015 June 2016 and Hope Creek Generating Stations - Cover Letter for Response to Request for Additional Information Regarding Review of Security Plan, Revision 17 LR-N16-0105, Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval2016-06-10010 June 2016 Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval LR-N15-0256, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-12-23023 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident LR-N15-0092, Compliance with NRC Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information2015-07-28028 July 2015 Compliance with NRC Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) and Responses to Requests for Additional Information 2024-04-26
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Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 G
Nuclear LLC 10 CFR 50.90 DEC 14 2017 LR-N17-0176 LAR H17-03 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (CAC NO. MF9930)
References 1. PSEG letter to NRC, "License Amendment Request for Measurement Uncertainty Recapture (MUR) Power Uprate," dated July 7, 2017 (ADAMS Accession No. ML17188A260)
- 2. NRC e-mail to PSEG, "HCGS MUR - Final Request for Additional Information
- Electrical Engineering (EEOB)," dated November 16, 2017 (ADAMS Accession No. ML17320A215)
In the Reference 1 letter, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment will increase the rated thermal power (RTP) level from 3840 megawatts thermal (MWt) to 3902 MWt, and make Technical Specification (TS) changes as necessary to support operation at the uprated power level.
In Reference 2, the U.S. Nuclear Regulatory Commission staff provided PSEG a Request for Additional Information (RAI) to support the NRC staff's detailed technical review of Reference 1.
PSEG has determined that the information provided in this submittal does not alter the conclusions reached in the 10 CFR 50.92 no significant hazards determination previously submitted. In addition, the information provided in this submittal does not affect the bases for
Page 2 10 CFR 50.90 LR*N17-0176 concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
No new regulatory commitments are established by this submittal. If you have any questions or require additional information, please do not hesitate to contact Mr. Brian Thomas at (856) 339-2022.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ----/JLr¥-'!_L(;
-Lt (Date)..JL.!/1.. (_._ _*-:;-L__* _
Respectfully, e-:0
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Eric Carr Site Vice President Hope Creek Generating Station
DEC I 412011 Page 3 10 CFR 50.90 LR*N17-0176 Attachment
- 1. Response to Request for Additional Information Regarding MUR Power Uprate cc: Mr. D. Dorman, Administrator, Region I, NRC Ms. L. Regner, Project Manager, NRC NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. MacEwen, Hope Creek Commitment Tracking Coordinator LAR H17-03 LR-N17-0176 Response to Request for Additional Information Regarding MUR Power Uprate
Attachment 1 LAR H17-03 LR-N17-0176 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE Hope Creek Generating Station Docket No. 50-354 CAC No. MF9930 By application dated July 7, 2017, Public Service Enterprise Group (PSEG), submitted a license amendment request (LAR) for Hope Creek Generating Station (HCGS). The proposed amendment would revise the Operating Licenses and Technical Specifications (TS) to implement a measurement uncertainty recapture (MUR) power uprate or thermal power optimization (TPO). Specifically, the proposed changes would increase the maximum licensed thermal power level from 3,840 megawatts thermal (MWt) to 3,902 MWt, which is an increase of approximately 1.6 percent.
The Electrical Engineering Operating Branch staff has reviewed the information provided by the licensee in the LAR. The following additional information is needed to complete our review of the LAR.
Regulatory Requirements: 10 CFR, Appendix A of Part 50, General Design Criterion (GDC) 17, "Electric Power Systems," requires, in part, that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are ,_
not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents. The onsite electric power supplies shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure.
EEOB-1 Section 6.1.2, "On-Site Power," of Enclosure 8 of the LAR states:
The only identifiable change in electrical load demand is associated with the condensate pumps. These pumps experience increased flow and a small change in horsepower duty due to the TPO uprate conditions. Accordingly, there are negligible changes in the on site distribution system design basis loads or voltages due to the TPO conditions.
Section 6.2, "DC Power," of Enclosure 8 of the LAR states:
The changes to the auxiliary power system as a result of the TPO uprate are small increases in the horsepower of the condensate pump and the reactor recirculation (RRC) pump motors.
The NRC staff notes that the TPO-related change in electrical load demand is identified as the increase in horsepower of the condensate pumps in Section 6.1.2. However, the change in electrical load demand is identified as the increase in horsepower of both the condensate pumps and the RRC pumps in Section 6.2. The NRC staff also noted that the licensee did not 1 of 4 LAR H17-03 LR-N17-0176 discuss the change in horsepower for these pumps due to the TPO uprate and the resulting change in the on-site distribution system design basis loads or voltages.
Provide a reason for this discrepancy and clarify which pumps that are impacted by the TPO uprate. Also provide the value or percentage increase in horsepower for the pumps impacted by the TPO uprate and discuss the effects of the increased horsepower on the associated safety-related and/or non-safety-related buses as a result of the TPO uprate.
Response
Both the condensate and reactor recirculation pump power is affected by TPO. The power increase in these pumps was evaluated as part of Hope Creek's previous Extended Power Uprate (EPU), submittal dated September 16, 2006 (ADAMS Accession No. ML062680447), at a bounding power level of 3952 MWt. For the EPU submittal, it was determined that the pump power at rated conditions was bounded by the load credited in design calculations. A summary of these values is included below:
Pump Motor Load @ 3952 MWt Design Calculation Load Reactor Recirc System M-G 7,313 BHP at 100% Core Flow 8,550 BHP Drive Motor 1AG120 8,094 BHP at 105% Core Flow Reactor Recirc System M-G 7,313 BHP at 100% Core Flow 8,550 BHP Drive Motor 1BG120 8,094 BHP at 105% Core Flow Primary Condensate Pump 1,120 BHP 1,423 BHP 1A-P-102 Primary Condensate Pump 1,120 BHP 1,423 BHP 1 8-P-102 Primary Condensate Pump 1,120BHP 1,500 BHP 1C-P-102 Secondary Condensate Pump 3,240 BHP 3,462 BHP 1A-P-137 Secondary Condensate Pump 3,240 BHP 3,462 BHP 1 8-P-137 Secondary Condensate Pump 3,240 BHP 3,650 BHP 1C-P-137 Therefore the existing analyses bound operation at TPO conditions of 3902 MWt and there is no effect on the analyzed loads for any electrical buses as a result of the TPO uprate.
EEOB-2 Section 10.3. 1.1, "Inside Containment," of Enclosure 8 of the LAR states:
EQ [environmental qualification] for safety-related electrical equipment located inside the containment is based on DBA-LOCA conditions and their resultant temperature, pressure, humidity and radiation consequences, and includes the environments expected to exist during normal plant operation. The current accident conditions for temperature and pressure are based on analyses initiated from at least 102% of CLTP.
Normal temperatures may increase slightly near the FW and RRC lines and will be 2 of 4 LAR H17-03 LR-N17-0176 evaluated through Section A.3.1.2 of UFSAR Appendix A, which addresses the existing program that manages the aging (EQ) of electrical equipment. The current radiation levels under normal plant conditions also increase slightly. The current plant environmental envelope for radiation is not exceeded by the changes resulting from the TPO uprate.
The licensee does not appear to have discussed the impact of the TPO uprate on all the environmental parameters for the safety-related equipment, and has not clearly stated whether the EQ electrical equipment remains qualified for the TPO uprate conditions.
Confirm that all existing environmentally qualified electrical equipment located inside and outside containment remain qualified for TPO uprate conditions during normal and accidents conditions. Include a basis for this response.
Response
The TPO uprate to 3902 MWt does not affect any environmental parameters for EQ equipment.
Section 6.6 of Enclosure 8 of the Hope Creek TPO LAR identifies that the increased heat loads in the drywell are within the capacity of the drywell cooling system. Normal area temperatures are based on the design specification of the drywell cooling system and any actual increases in local temperatures are bounded by the analyzed area temperature.
The design basis accident containment temperature and pressure conditions were determined for EPU using a core thermal power of 4031 MWt (1.02 x 3952 MWt), with the exception of peak bulk suppression pool temperature, which was determined at 3917 MWt (1.02 x 3840 MWt).
The results are documented in Table 4-1 of NEDC-33076P, "Safety Analysis Report for Hope Creek Constant Pressure Power Uprate," submitted as Attachment 4 to the Hope Creek EPU license amendment request (ADAMS Accession No. ML062680447). These results bound operation at TPO conditions. EQ testing is performed using bounding pressure and temperature profiles with peak values of 62 psig and 340°F, which bound the accident pressure and temperature conditions for TPO.
Design basis accident containment humidity is conservatively assumed to be 100% for 100 days. EQ equipment is tested to 100% humidity.
The current normal radiation dose is based on a core thermal power of 3952 MWt and a plant life of 60 years. Any actual increases in normal dose rates are bounded by analyzed dose rates.
The design basis accident containment radiation conditions were determined for EPU using a core thermal power of 3917 MWt (1.02 x 3840 MWt). This value bounds the TPO uprate power level, including heat balance uncertainty.
The existing analyses bound operation at TPO conditions. All EQ electrical equipment remains qualified for TPO uprate conditions under normal and accident conditions.
3 of 4 LAR H17-03 LR-N17-0176 EEOB-3 Section 3.4.5, "Grid Stability Studies," of Enclosure 1 of the LAR states:
Grid stability studies were performed for Hope Creek operation at a bounding electrical power output of 1320 [Megawatts electrical] MWe. These results bound operation at the proposed MUR power level of 3902 [Megawatts thermal] MWt."
The licensee has not provided the proposed MUR power level in MWe to allow the staff to verify that the MWe used for the grid studies is bounding for the TPO uprate.
Provide the value of the MWe power corresponding to the proposed MUR power level of 3902 MWt and include uncertainties, if any.
Response
The existing grid stability study determines operating curves for the Hope Creek generator under multiple postulated grid conditions. This study provides operating curves with a maximum MWe output of 1320 MWe under normal conditions. Existing operating procedures direct control room operators to maintain electrical output below the operating curves.
The relationship between core thermal power and generator MWe output is dependent on multiple variables, primarily circulating water inlet temperature. At the current licensed thermal power (CL TP) of 3840 MWt, generator output has historically varied between approximately 1220 MWe and 1306 MWe. Under TPO power uprate conditions, approximately 20 additional MWe are expected. If plant conditions allow generator output to approach 1320 MWe, operators will decrease reactor power to maintain the generator output below the allowed operating curves.
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