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Category:Letter
MONTHYEARIR 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 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 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 IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) 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 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 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 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations 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) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 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 ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations 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 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 IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) 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 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 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 ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
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 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 ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) 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 ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan 2024-01-16
[Table view] Category:Safety Evaluation
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 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) ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 2024-01-16
[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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 August 6, 2019 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT NO. 217 RE: REMOTE SHUTDOWN SYSTEM (EPID L-2018-LLA-0295)
Dear Mr. Carr:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 217 to Renewed Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek) in response to your application dated October 30, 2018.
The amendment revises Technical Specification 3.3.7.4, "Remote Shutdown System Instrumentation and Controls," to make the Hope Creek Generating Station requirements consistent with Standard Technical Specification 3.3.3.2, "Remote Shutdown System" in NUREG-1433, Volume 1, Revision 4. The change increases the allowed outage time for inoperable remote shutdown system components to a time that is more consistent with their safety significance. Also, the amendment deletes Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocates them to the Technical Requirements Manual where they will be directly controlled by Hope Creek.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Amendment No. 217 to Renewed License No. NPF-57
- 2. Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 Renewed License No. NPF-57
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by PSEG Nuclear LLC dated October 30, 2018, 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 Gan 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.
Enclosure 1
- 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. 217, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed 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 of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jame G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 6, 2019
ATTACHMENT TO LICENSE AMENDMENT NO. 217 HOPE CREEK GENERATING STATION RENEWED FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of the Renewed Facility Operating License with the revised page.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 3
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert viii viii ix ix 3/4 3-74 3/4 3-74 3/4 3-75 3/4 3-75 through 3/4 3-83 3/4 3-76 (deletion page) 3/4 3-77 3/4 3-78 3/4 3-79 3/4 3-80 3/4 3-81 3/4 3-82 3/4 3-83
reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation.
(7) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
( 1) Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3902 megawatts thermal ( 100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 217, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-57 Amendment No. 217
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Table 3.3.5-1 Reactor Core Isolation Cooling System Actuation Instrumentation . . . . . . . . . . . . . . . . . . . . 3/4 3-52 Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation Setpoints .......... 3/4 3-54 Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-55 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-56 Table 3.3.6-1 Control Rod Block Instrumentation ............ 3/4 3-57 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 3-59 Table 4.3.6-1 Control Rod Block Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . . . 3/4 3-60 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-62 Table 3.3.7.1-1 Radiation Monitoring Instrumentation ....... 3/4 3-63 Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . 3/4 3-66 Remote Shutdown System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 3-7 4 HOPE CREEK viii Amendment No. 217
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Accident Monitoring Instrumentation . . . . . 3/4 3-84 Table 3.3.7.5-1 Accident Monitoring Instrumentation . . . . . 3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements 3/4 3-87 Source Range Monitors . . 3/4 3-88 3/4.3.8 DELETED . . . . . . . . . . 3/4 3-103 3/4.3.9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-105 Table 3.3.9-1 Feedwater/Main Turbine Trip System Actuation Instrumentation . . . . . 3/4 3-106 HOPE CREEK ix Amendment No. 217
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.4 The remote shutdown system functions shall be OPERABLE.
APPLICABILITY OPERATIONAL CONDITIONS 1 and 2.
NOTE--------------------------------------------------------
Sepa rate ACTION entry is allowed for each Function ACTION:
- a. With one or more of the required functions inoperable, restore the inoperable function(s) to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.3.7.4.1 Each normally energized required instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at the frequency specified in the Surveillance Frequency Control Program.
4.3.7.4.2 Each required control circuit and transfer switch shall be demonstrated OPERABLE by verifying its capability to perform its intended function in accordance with the Surveillance Frequency Control Program.
4.3.7.4.3 Each required instrumentation channel° shall be demonstrated OPERABLE by performance of a CHANNEL CALIBRATION at the frequency specified in the Surveillance Frequency Control Program.
Safety Relief Valve Position, Standby Diesel Generator Breaker Indication, and Switchgear Room Cooler Status Indication are excluded from CHANNEL CALIBRATION.
HOPE CREEK 3/4 3-74 Amendment No. 217
Pages 3/4 3-75 through 3/4 3-83 intentionally deleted HOPE CREEK 3/4 3-75 through 3/4 3-83 Amendment No. 217
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-57 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354
1.0 INTRODUCTION
By letter dated October 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18304A191), PSEG Nuclear LLC (the licensee) requested U.S. Nuclear Regulatory Commission (NRC or the Commission) approval for a license amendment request (LAR) to revise the Hope Creek Generating Station (Hope Creek)
Technical Specifications (TSs). The LAR proposes to revise TS 3.3.7.4, "Remote Shutdown System Instrumentation and Controls," to make the Hope Creek requirements consistent with Standard Technical Specification (STS) 3.3.3.2, "Remote Shutdown System." The change would increase the allowed outage time for inoperable remote shutdown system components from 7 days to 30 days. Also, the amendment would delete Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocate them to the Technical Requirements Manual (TRM) where they would be directly controlled by Hope Creek.
2.0 REGULATORY EVALUATION
2.1 Description of the Remote Shutdown System The remote shutdown system (RSS) provides the means for achieving and maintaining safe shutdown conditions from outside the main control room in the unlikely event that the main control room becomes uninhabitable. The primary control station for the RSS is the remote shutdown panel. In the event of a failure at the remote shutdown panel, sufficient redundant safety grade instrumentation and controls are available remotely from both the main control room and the remote shutdown panel to ensure that safe shutdown of the reactor can be achieved in accordance with the requirements of Title 10 of the Code of Federal Regulations (1 O CFR), Part 50, Appendix A, "General Design Criteria [GDC] for Nuclear Power Plants,"
Criterion 19 (GDC 19).
2.2.1 Description of Proposed Changes
- 1. Revise TS 3.3. 7.4 Limiting Condition for Operation (LCO) to state that the Remote Shutdown System functions shall be OPERABLE. Delete references to Enclosure 2
Tables 3.3. 7.4-1 and 3.3.7.4-2 listing the specific instruments and controls for the remote shutdown system. The proposed change will relocate information in these tables to licensee-controlled documents.
- 2. Revise TS 3.3.7.4 ACTION a. to delete the reference to monitoring instrumentation channels as shown in the associated Table 3.3.7.4-1. The action will be simplified to state the entry condition for the action as "one or more of the required functions inoperable." Add a note to permit separate condition entry for each function.
- 3. Revise TS 3.3.7.4 ACTION a. to change the required action time from 7 days to 30 days.
- 4. Delete TS 3.3. 7.4 ACTION b.
- 5. Delete Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocate the remote shutdown system equipment information to the TRM.
- 6. Revise Surveillance Requirement (SR) 4.3. 7.4.1 to:
a) delete reference to Table 4.3.7.4-1, which is being deleted; b) relocate channel calibration to a new SR 4.3.7.4.3; c) require the channel check only for normally energized remote shutdown system instrumentation; and e) replace "the" with "a."
- 7. Revise SR 4.3.7.4.2 replacing "At least one of each of the above remote shutdown switch(es) and control circuits" with "each required control circuit and transfer switch."
- 8. Add new section SR 4.3.7.4.3, stating the following: "Each required instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CALIBRATION at the frequency specified in the Surveillance Frequency Control Program."
- 9. Add a note to SR 4.3.7.4.3 that the safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication are excluded from channel calibration;
- 10. Revise TS Index pages viii and ix to reflect the TS Section 3.3.7.4 title and deletion of the tables.
2.3 Regulatory Requirements Section 50.36 of 10 CFR, "Technical specifications," identifies the requirements for the TS categories for operating power plants. Of the six requirements, the following two are applicable to this review:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
Appendix A to 10 CFR Part 50, GDC 19, "Control room," states, in part:
Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.
2.4 Regulatory Guidance NUREG-1433, Volume 1, Revision 4, "Standard Technical Specifications, General Electric BWR/4 Plants" (ADAMS Accession No. ML12104A192).
3.0 TECHNICAL EVALUATION
3.1 Revision to TS 3.3.7.4 LCO for the Remote Shutdown System GDC 19 requires that the licensee provide remote shutdown capability. The remote shutdown system functions are described in the Updated Final Safety Analysis Report.
The licensee has requested a revision to TS 3.3. 7.4 LCO to state that the remote shutdown system functions shall be operable. The revision would delete references to instrumentation as shown in the associated Tables 3.3.7.4-1 and 3.3.7.4-2. In Section 3.3.7.4 of the current TSs, Tables 3.3. 7.4-1, 3.3. 7.4-2, and 4.3. 7.4-1 list the specific instruments and controls for the remote shutdown system. The proposed change would relocate these requirements to licensee-controlled documents.
The definition of operable in NUREG-1433 states that a system shall be operable or have operability "when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system to perform its specified safety function(s) are also capable of performing their related support function." This definition provides adequate guidance for determining what instrumentation and controls are necessary for a particular remote shutdown function. The ability to transfer control of a function from the main control room to the auxiliary shutdown panel is a required support function by the TS definition of operable. Therefore, listing specific instrumentation and controls is unnecessary
and may lead to needless expenditure of licensee and NRC resources, processing license amendments to revise the remote shutdown system details in TS Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1. These details are not necessary to describe the actual regulatory requirements.
Moreover, SR 4.3. 7.4.2 still requires the local panel transfer function to be tested, which is sufficient to assure that the system will be operable. Relocation of the list of variables to the TRM is acceptable because the TRM is consistent with the design basis as described in the Updated Final Safety Analysis Report. Therefore, it can be relocated to the TRM without a significant safety impact. Changes to the TRM are evaluated in accordance with 10 CFR 50.59 requirements.
In addition, precedent for the relocation has been established with Technical Specifications Task Force (TSTF} Traveler TSTF-266, "Eliminate the Remote Shutdown System Table of Instrumentation and Controls," and Revision 2 of NUREG-1433, which incorporated TSTF-266 into the Improved STS. Moreover, relocation of the subject list of variables to the TRM is acceptable because its inclusion in the TSs does not fall within the criteria for mandatory inclusion in the TSs in 10 CFR 50.36(c)(2)(ii). The NRC staff finds that sufficient regulatory controls exist under the regulations to maintain the effect of the provisions in the TRM. Based on the above evaluation, the NRC staff finds that the proposed change is acceptable.
3.2 Revision to TS 3.3.7.4 Action The licensee has proposed a revision to TS 3.3. 7.4 ACTION a. to delete the reference to monitoring instrumentation channels as shown in the associated Table 3.3.7.4-1. The action will be simplified to state the entry condition for the action as:
With one or more of the required functions inoperable, restore the inoperable function to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />." A note would be added to permit "Separate ACTION entry is allowed for each Function.
The proposed deletion of the references to monitoring instrumentation is acceptable for the reasons discussed in Section 3.1 above. Adding a note of "Separate ACTION entry is allowed for each Function," to the current TS would permit separate entry into the required action, should more than one function be inoperable. Without the proposed note, the new wording could be interpreted as not allowing separate entry for each function; thus, entry into the required actions for an inoperable channel of a second function would result in a plant shutdown per LCO 3.0.3. The proposed note is consistent with NUREG-1433. The NRC staff finds that these changes will ensure that the inoperable equipment is restored to an operable status and conversely provide reasonable assurance that the licensee will comply with the regulations.
3.3 TS 3.3. 7.4 Action Time Change The licensee proposed to revise TS 3.3. 7.4 ACTION a. to change the required action time from 7 days to 30 days.
The proposed change in action time from 7 days to 30 days is based on operating experience and the low probability of an event occurring that would require the control room to be evacuated. In addition, precedent for extending the allowed outage time to 30 days has been established with TSTF-266 and Revision 2 of NUREG-1433, which incorporated TSTF-266 into the Improved STS. The NRC staff finds that this proposed change is acceptable.
3.4 Deletion of TS 3.3.7.4 Action The licensee proposed to delete TS 3.3.7.4 ACTION b., which states:
With the number of OPERABLE remote shutdown system controls less than required in Table 3.3.7.4-2, restore the inoperable control(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Table 3.3.7.4-2 is being deleted, as discussed in Section 3.1 above, and relocated to a licensee-controlled document; reference to it is no longer applicable. TS 3.3.7.4 ACTION a.
was revised to add the wording "one or more required functions," which now encompasses the required actions of TS 3.3. 7.4 ACTION b. ACTION a. will continue to meet the requirements for an inoperable remote shutdown system control; therefore, TS 3.3. 7.4 ACTION b. is no longer needed. The NRC staff finds that this proposed change is acceptable.
3.5 Deletion of Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1 The licensee has proposed to delete Tables 3.3. 7.4-1, 3.3. 7.4-2, and 4.3. 7.4-1 and relocate the remote shutdown system equipment information to the TRM. The NRC staff reviewed the proposed changes and found them acceptable for the reasons discussed in Section 3.1 above.
3.6 Revisions to SR 4.3. 7.4.1 and add SR 4.3. 7.4.3 The NRC staff's evaluation of the licensee-proposed changes to SR 4.3.7.4.1 and the addition of SR 4.3.7.4.3 is as follows:
a) The licensee proposed to remove reference to Table 4.3. 7.4-1, which was proposed to be deleted. The NRC staff finds this change acceptable for reasons discussed in Section 3.1 above.
b) The licensee proposed to relocate channel calibration to a new SR 4.3.7.4.3.
Currently, the SR to perform a channel calibration is located in SR 4.3.7.4.1.
The licensee stated in the LAR that splitting out the channel calibration into a new SR (4.3.7.4.3) and rewording the SR makes it consistent with the Improved STS. The NRC staff reviewed the change and determined that relocating the channel calibration to SR 4.3. 7.4.3 continues to meet the requirements of 10 CFR 50.36(c)(3) for channel calibration of instrument channels because the proposed SR effectively maintains the existing TS requirement for a channel calibration. Therefore, the change is acceptable.
c) The licensee proposed to add the statement "normally energized" to SR 4.3.7.4.1. This change would require the channel check only for normally energized remote shutdown system instrumentation. The licensee stated in the LAR that performing a channel check of normally deenergized instrumentation is not practical or feasible during power operation. This change is consistent with Improved STS SR 3.3.3.2.1. The NRC staff finds the proposed change to the TS acceptable.
d) Add a note to SR 4.3. 7.4.3 that the safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication are
excluded from channel calibration. The note makes the remote shutdown system consistent with the requirements already established for safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication in current TS Table 4.3. 7.4-1. The NRC staff finds the proposed change to the TS acceptable.
e) Replace "the" with "a" in SR 4.3.7.4.1. This is an administrative change to ensure that, with the revisions mentioned above, the SR remains grammatically correct. Therefore, the proposed change is acceptable.
3.7 Revisions to SR 4.3.7.4.2 The licensee proposed to revise SR 4.3. 7.4.2 by replacing "At least one of each of the above remote shutdown switch(es) and control circuits" with "each required control circuit and transfer switch." The licensee stated that these changes make the SR wording consistent with Improved STS SR 3.3.3.2 and reflect the removal of TS Table 3.3. 7.4-2. The NRC staff reviewed the changes and determined that the proposed revision to SR 4.3. 7.4.2 is functionally equivalent to the existing SR and demonstrated that the required control circuit and control switch be operable. Therefore, the NRC staff finds this change acceptable.
3.8 Revisions to TS Index Pages The licensee proposed to revise TS Index pages viii and ix to reflect the TS Section 3.3.7.4 title and the deletion of the tables. This change is being made for consistency, does not affect any requirements associated with the remote shutdown system, and is acceptable.
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 on June 7, 2019. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, and changes surveillance requirements. 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 (83 FR 64897). 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 assessment 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) there is reasonable assurance that 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: T. Sweat Date: August 6, 2019
SUBJECT:
HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT NO. 217 RE: REMOTE SHUTDOWN SYSTEM (EPID L-2018-LLA-0295)
DATED AUGUST 6, 2019 DISTRIBUTION:
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NAME JKim KEntz LRonewicz PSnyder DATE 07/19/2019 07/16/2019 07/19/2019 07/01/2019 OFFICE OGC- NLO** NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JScro Joanna JKim DATE 07/30/2019 08/02/2019 08/06/2019 OFFICIAL RECORD COPY