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Category:Letter
MONTHYEARIR 05000272/20244032024-09-25025 September 2024 and Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) IR 05000272/20244022024-09-23023 September 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML24197A0552024-07-15015 July 2024 Requalification Program Inspection LR-N24-0048, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) 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 IR 05000272/20245012024-06-12012 June 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 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 ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 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 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 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 IR 05000272/20240112024-04-0101 April 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 – Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) 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 ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary 2024-09-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML23341A1372024-01-16016 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 ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report ML22194A8172022-08-10010 August 2022 Issuance of Amendment No. 232 Revise Surveillance Requirements for Electric Power Monitor Channels for Reactor Protection System and Power Range Neutron Monitoring System ML21348A7132022-03-14014 March 2022 Issuance of Amendment No. 231 Revision of Technical Specification Limits for Ultimate Heat Sink ML22056A0102022-03-0404 March 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Correction Letter of Amendment Nos. 230, 342, and 323 Deletion of Specified Definitions and Figures ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML21341B4262021-12-0808 December 2021 Correction Letter of Amendment No. 229 Revise Low Pressure Safety Limit to Address General Electric Nuclear Energy Part 21 Safety Communication SC05-03 ML21181A0562021-08-17017 August 2021 Issuance of Amendment No. 229 Revise Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03 (EPID L 2020 Lla 0210) (Non-Proprietary) ML21098A0872021-04-26026 April 2021 Issuance of Amendment No. 228 Adopt Technical Specifications Task Force TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability 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 ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19289A8862019-11-0707 November 2019 Issuance of Amendment No. 220 Regarding Revise Technical Specifications to Adopt TSTF-546, Revise APRM (Average Power Range Monitor) Channel Adjustment Surveillance Requirement ML19218A3052019-09-19019 September 2019 Issuance of Amendment No. 219 Regarding Revise Technical Specifications to Adopt TSFF-564, Safety Limit MCPR ML19205A3062019-09-0606 September 2019 Issuance of Amendment No. 218 Regarding Revised Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19073A0732019-04-30030 April 2019 Issuance of Amendment No. 216 Revise Technical Specification 3/4.8.1, A.C. Sources - Operating, Action for Inoperable Diesel Generator ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML18260A2032018-10-30030 October 2018 Issuance of Amendment No. 213 Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) ML18081A0442018-04-11011 April 2018 Issuance of Amendment No. 211 Safety Limit Minimum Critical Power Ratio Change ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17324A8402017-12-14014 December 2017 Issuance of Amendment to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report (CAC No. MF9502; EPID L-2017-LLA-0204) ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17291A2092017-11-0808 November 2017 Issuance of Amendment Technical Specification Change for Permanent Extension to Type a and Type C Containment Leak Rate Test Frequencies (CAC No. MF8462; EPID L-2016-JLD-0011) ML17216A0222017-08-0404 August 2017 Nonproprietary Issuance of Amendment Regarding Digital Power Range Neutron Monitoring System Upgrade ML17164A3552017-06-28028 June 2017 Issuance of Amendment 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 ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule 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 ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments 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 ML14323A9742014-12-23023 December 2014 and Salem Nuclear Generating Station, Units 1 and 2, Issuance of Amendments Revision to Cyber Security Plan Implemenation Schedule and Conditions ML14108A3992014-12-18018 December 2014 Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual ML14108A3122014-07-29029 July 2014 Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual ML13114A0782013-06-26026 June 2013 Issuance of Amendment Request for Technical Specification Change to Average Power Range Monitoring System Operability Requirements in Operating Condition 5 ML12335A2212012-12-10010 December 2012 and Salem Nuclear Generating Station, Units 1 and 2 - Issuance of Amendments Approval of Change to Implementation Milestone 6 of Cyber Security Plan LR-N12-0107, License Amendment Request - APRM Operability Requirements in Opcon 52012-06-0606 June 2012 License Amendment Request - APRM Operability Requirements in Opcon 5 ML1201800782012-02-0808 February 2012 Issuance of Amendment 191 Control Room Emergency Filtration System and Control Room Air Conditioning System ML1123806182011-09-14014 September 2011 Issuance of Amendment Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out of Service 2024-07-15
[Table view] Category:Safety Evaluation
MONTHYEARML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML23341A1372024-01-16016 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 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report ML22194A8172022-08-10010 August 2022 Issuance of Amendment No. 232 Revise Surveillance Requirements for Electric Power Monitor Channels for Reactor Protection System and Power Range Neutron Monitoring System ML22194A8402022-07-15015 July 2022 Correction Letter of Relief Request No. HR-I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs ML22181A1252022-07-0505 July 2022 Issuance of Relief Request No. HR I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs ML21348A7132022-03-14014 March 2022 Issuance of Amendment No. 231 Revision of Technical Specification Limits for Ultimate Heat Sink ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML21181A0562021-08-17017 August 2021 Issuance of Amendment No. 229 Revise Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03 (EPID L 2020 Lla 0210) (Non-Proprietary) ML21098A0872021-04-26026 April 2021 Issuance of Amendment No. 228 Adopt Technical Specifications Task Force TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability 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 ML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20091L9992020-04-13013 April 2020 Issuance of Relief Request HC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval 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 ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19289A8862019-11-0707 November 2019 Issuance of Amendment No. 220 Regarding Revise Technical Specifications to Adopt TSTF-546, Revise APRM (Average Power Range Monitor) Channel Adjustment Surveillance Requirement ML19218A3052019-09-19019 September 2019 Issuance of Amendment No. 219 Regarding Revise Technical Specifications to Adopt TSFF-564, Safety Limit MCPR ML19220A1022019-09-0606 September 2019 Alternative Request VR-03 to Use ASME Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valve for the Fourth 10-Year Inservice Test Interval ML19205A3062019-09-0606 September 2019 Issuance of Amendment No. 218 Regarding Revised Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19136A0262019-07-11011 July 2019 Issuance of Relief Request No. HC-I3R-08, Revision 0, Use of the ASME Code ML19073A0732019-04-30030 April 2019 Issuance of Amendment No. 216 Revise Technical Specification 3/4.8.1, A.C. Sources - Operating, Action for Inoperable Diesel Generator ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML18290A8762018-12-0606 December 2018 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4458; EPID No. L-2014-JLD-0040) ML18260A2032018-10-30030 October 2018 Issuance of Amendment No. 213 Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) ML18081A0442018-04-11011 April 2018 Issuance of Amendment No. 211 Safety Limit Minimum Critical Power Ratio Change ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17324A8402017-12-14014 December 2017 Issuance of Amendment to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report (CAC No. MF9502; EPID L-2017-LLA-0204) ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17321B1062017-11-28028 November 2017 Request to Use Later Edition of American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC No. MG0124; EPID L-2017-LLR-0087) ML17291A2092017-11-0808 November 2017 Issuance of Amendment Technical Specification Change for Permanent Extension to Type a and Type C Containment Leak Rate Test Frequencies (CAC No. MF8462; EPID L-2016-JLD-0011) ML17223A4832017-08-17017 August 2017 Relief from the Requirements of the ASME Code for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations ML17216A0222017-08-0404 August 2017 Nonproprietary Issuance of Amendment Regarding Digital Power Range Neutron Monitoring System Upgrade ML17125A2662017-06-30030 June 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17164A3552017-06-28028 June 2017 Issuance of Amendment 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 ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule 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 ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16343A0572016-12-20020 December 2016 Requests for Relief GR-01, PR-01, PR-02, VR-01, and VR-02, for the Fourth Inservice Testing Interval ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML16256A6552016-09-30030 September 2016 Hope Creek Generating Station - Request for Relaxation of the Release Point Height Requirement of NRC Order EA-13-109,Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML16259A2042016-09-20020 September 2016 Hope Creek Generating Station - Safety Evaluation - Request to revise technical specifications - safety limit minimum critical power ratio.(TAC NO. MF7793) 2024-07-15
[Table view] |
Text
October 16, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE:
REMOVAL OF TURBINE FIRST STAGE PRESSURE VALUES FROM TECHNICAL SPECIFICATIONS (TAC NO. MD6165)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment No. 172 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station. This amendment consists of changes to
the Technical Specifications (TSs) in response to your application dated July 26, 2007. The
amendment removes values for turbine first stage pressure associated with Pbypass from the TSs.
Pbypass is the reactor power level below which the turbine stop valve closure and the turbine control valve fast closure reactor protection system trip functions and the end-of-cycle
recirculation pump trip are bypassed automatically.
A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the
Commission's biweekly Federal Register notice. Sincerely, /ra/ Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Amendment No. 172 to License No. NPF-57
- 2. Safety Evaluation cc w/encls: See next page October 16, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT RE:
REMOVAL OF TURBINE FIRST STAGE PRESSURE VALUES FROM TECHNICAL SPECIFICATIONS (TAC NO. MD6165)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment No. 172 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station. This amendment consists of changes to
the Technical Specifications (TSs) in response to your application dated July 26, 2007. The
amendment removes values for turbine first stage pressure associated with Pbypass from the TSs.
Pbypass is the reactor power level below which the turbine stop valve closure and the turbine control valve fast closure reactor protection system trip functions and the end-of-cycle
recirculation pump trip are bypassed automatically.
A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the
Commission's biweekly Federal Register notice. Sincerely, /ra/ Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Amendment No. 172 to License No. NPF-57
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION
- PUBLIC RidsOgcRp LPL1-2 R/F RidsAcrsAcnwMailCenter RidsNrrDorlLpl1-2 RidsNrrDirsltsb RidsNrrLASLittle RidsRgn1MailCenter RidsNrrPMREnnis GHill (2), OIS RidsNrrDorlDPR RidsNrrLAABaxter Package Accession No.: ML072480010 Amendment Accession No: ML072480022 TS Accession No.: ML072850037 O FFICE L PL1-2/PM L PL1-2/LA L PL1-1/LA E ICB/BC O GC L PL1-2/BC N AME R Ennis A Baxter S Little W Kemper E Williamson H Chernoff DATE 9/5/07 9/6/07 9/17/07 9/24/07 10/3/07 10/16/07 OFFICIAL RECORD COPY Hope Creek Generating Station cc: Mr. Thomas Joyce Senior Vice President - Operations PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Dennis Winchester Vice President - Nuclear Assessment PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. George Barnes Site Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Vice President - Operations Support PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John Perry Plant Manager - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Michael Gaffney Manager - Hope Creek Regulatory Assurance PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Hope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038
PSEG NUCLEAR LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amend ment No. 172 License No. NPF-57
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by PSEG Nuclear LLC dated July 26, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in
10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the
public, and (ii) that such activities will be conducted in compliance with the
Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility
Operating License No. NPF-57 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 172, and the Environmental Protection Plan contained in
Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall
operate the facility in accordance with the Technical Specifications and the
Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/ Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and the Technical Specifications Date of Issuance: October 16, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 172 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of Facility Operating License No. NPF-57 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal
lines indicating the areas of change.
Remove InsertPage 3 Page 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached
revised pages as indicated. The revised pages are identified by amendment number and
contain marginal lines indicating the areas of change.
Remove Insert3/4 3-5 3/4 3-5 3/4 3-47 3/4 3-47 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 172 TO FACILITY OPERATING LICENSE NO. NPF-57 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354
1.0 INTRODUCTION
By letter dated July 26, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072150248), PSEG Nuclear LLC (the licensee) requested changes to the Hope Creek Generating Station (HCGS) Technical Specification (TSs). The proposed
amendment would remove values for turbine first stage pressure associated with Pbypass from the TSs. Pbypass is the reactor power level below which the turbine stop valve (TSV) closure and the turbine control valve (TCV) fast closure reactor protection system (RPS) trip functions and the
end-of-cycle recirculation pump trip (EOC-RPT) are bypassed automatically.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission
=s (NRC=s or the Commission
=s) regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, A Technical specifications.
@ This regulation requires that the TSs include items in five specific categories. These categories include (1) safety limits, limiting
safety system settings and limiting control setti ngs, (2) limiting conditions for operation (LCOs), (3) surveillance requirements (SRs), (4) design features, and (5) administrative controls.
However, the regulation does not specify the particular TSs to be included in a plant
=s TSs. Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether an
LCO is required to be included in TSs. These criteria are:
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
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.
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.
Criterion 4: A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Existing LCOs and related SRs included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs. Those TS requirements which do not satisfy these
criteria may be relocated to other licensee-controlled documents.
3.0 TECHNICAL EVALUATION
The RPS is designed to cause rapid insertion of control rods (i.e., scram) to shutdown the
reactor when specific parameters exceed predet ermined limits. For HCGS, the parameters providing input to the RPS scram logic are shown in TS Table 3.3.1-1, A Reactor Protection System Instrumentation.
@ Two of the monitored parameters include TSV closure and TCV fast closure.
The TSV closure RPS trip function is discussed in Section 7.2.1.1.4 of the HCGS Updated Final
Safety Analysis Report (UFSAR). A turbine trip initiates closure of the TSVs, which can result in
a significant addition of positive reactivity to the core as the reactor pressure rise causes steam
voids to collapse. The TSV closure RPS trip initiates a reactor scram earlier than either the neutron monitoring system trip or reactor vessel high pressure trip to provide the required safety
margin below core thermal-hydraulic limits for this abnormal operational transient.
The TCV fast closure RPS trip function is discussed in Section 7.2.1.1.5 of the HCGS UFSAR.
A generator load rejection, with reactor power above 30% of RTP, or a turbine trip automatically
initiates a fast closure of the TCVs. Fast closure of the TCVs results in a situation similar to
closure of the TSVs and, as such, the TCV fast closure RPS trip is provided for the same
reasons as those discussed above for the TSV closure RPS trip.
The instrumentation associated with the EOC-RPT is discussed in Section 7.6.1.5 of the HCGS
UFSAR. The EOC-RPT instrumentation initiates tripping of both recirculation pumps based on
inputs from the RPS logic associated with closure of the TSVs or fast closure of the TSVs. The
reason for tripping the recirculation pumps is to reduce the impact on the fuel of thermal
transients caused by a turbine trip, generator trip, or load rejection. The rapid core flow
reduction increases void content and thereby introduces negative reactivity in conjunction with
control rod insertion.
The TSV closure and TCV fast closure RPS trip functions and the EOC-RPT function are
bypassed automatically if turbine first stage pressure is less than a pressure corresponding to
30% of rated thermal power (RTP). The intent of this automatic bypass (which is designated as
Pbypass) is to reduce scrams and recirculation pump trips at low power levels where the turbine steam bypass system is effective for turb ine trips and generator load rejections.
TS LCO 3.3.1 requires the RPS instrumentation channels to be operable as specified by TS
Table 3.3.1-1. TS Table 3.3.1-1 requires that the TSV closure and TCV fast closure RPS trip
functions be operable in operational condition 1 (i.e., power operation). The applicable
operational condition for these functions is modified by note A j@ which currently reads as follows:
This function shall be automatically bypassed when turbine first stage pressure is 159.7 psig [pounds per square inch gauge] equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER. To allow for instrument accuracy, calibration, and
drift, a setpoint of 135.7 psig is used.
TS LCO 3.3.4.2 requires the EOC-RPT syst em instrumentation channels shown in TS Table 3.3.4.2-1 to be operable in operational condition 1 when thermal power is greater than or
equal to 30% of RTP. TS Table 3.3.4.2-1, note A b@ currently states that:
This function shall be automatically bypassed when turbine first stage pressure is 159.7 psig equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER. To allow for instrument accuracy, calibration and drift, a setpoint of 135.7 psig is used.
The licensee's application dated July 26, 2007, states that modifications to the high-pressure
turbine, planned to be performed during the fall 2007 refueling outage, will change the
relationship between turbine first stage pressure and RTP. To support this planned
modification, the proposed amendment would revise note A j@ in TS Table 3.3.1-1 and note A b@ in TS Table 3.3.4.2-1 to remove the values for turbine first stage pressure. Specifically, the notes
would read as follows:
This function shall be automatically bypassed when turbine first stage pressure is
equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.
The licensee
=s application dated July 26, 2007, states that the turbine first stage pressure values in TS Tables 3.3.1-1 and 3.3.4.2-1 are details of system design that are not required by
10 CFR 50.36(c)(2)(ii) to be included in the TSs because:
- 1. Turbine first stage pressure instrumentation is not used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant
pressure boundary.
- 2. Turbine first stage pressure is not 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. Pbypass is an initial condition for some transient analyses and is retained in TS Tables 3.3.1-1 and 3.3.4.2-1.
- 3. Turbine first stage pressure instrumentation is not 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.
- 4. Turbine first stage pressure instrumentation is not a structure, system, or component which operating experience or probabilistic risk assessment has
shown to be significant to public health and safety.
The application dated July 26, 2007, also states that a turbine first stage pressure setpoint will be established in accordance with plant procedures before plant startup to ensure compliance
with the TS requirements. Testing will be performed to confirm the turbine first stage pressure
at Pbypass during the plant startup after the fall 2007 outage.
In addition to the sections in Chapter 7 of the HCGS UFSAR referenced above, the NRC staff
reviewed the following portions of Chapter 15 of the HCGS UFSAR which describe the
applicable transient analyses:
- 1) Section 15.2.2, A Generator Load Rejection
@ 2) Section 15.2.3, A Turbine Trip
@ 3) Section 15.9.6.3, A Anticipated Operational Transients
@ 4) Section 15.9.6.4, A Abnormal Operational Transients
@ 5) Figure 15.9-32, A Protection Sequences for Main Turbine Trip with Bypass
@ 6) Figure 15.9-34, A Protection Sequences for Main Generator Trip with Bypass System Operation@ 7) Figure 15.9-36, A Protection Sequences for Main Generator Trip with Bypass System Failure
@ 8) Figure 15.9-37, A Protection Sequences for Main Turbine Trip with Bypass System Failure
@ The UFSAR transient analyses noted above are based, in part, on the assumption that the TSV
closure and TCV fast closure RPS trip functions and the EOC-RPT function are operable at or
above 30% of RTP. The transient analyses do not discuss the turbine first stage pressure
values in terms of psig.
Based on review of the HCGS UFSAR, the NRC staff agrees with the licensee
=s determination that the turbine first stage pressure values in TS Tables 3.3.1-1 and 3.3.4.2-1 are details of
system design that are not required by 10 CFR 50.36(c)(2)(ii) to be included in the TSs. The
NRC staff also finds that the provisions of 10 CFR 50.59 provide adequate control to establish
the turbine first stage pressure setpoint in the associated plant procedures. Based on these
considerations, the NRC staff concludes that the proposed amendment is acceptable.
The NRC staff notes that removal of the turbine first stage pressure values from the TSs is
consistent with NUREG-1433, Revision 3, A Standard Technical Specifications, General Electric Plants BWR/4.
@
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State Official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has
determined that the amendment involves no significant increase in the amounts, and no
significant change in the types, of any effluents that may be released offsite, and that there is no
significant increase in individual or cumulative occupational radiation exposure. The
Commission has previously issued a proposed finding that the amendment involves no
significant hazards consideration, and there has been no public comment on such finding (72 FR 45460). Accordingly, the amendment meets the eligibility criteria for categorical
exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental
impact statement or environmental assessm ent need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (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.
Principal Contributor: R. Ennis Date: October 16, 2007