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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:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 2023-09-06
[Table view] Category:Miscellaneous
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML12220A2502012-08-10010 August 2012 Closeout of Bulletin 2011-01, Mitigating Strategies ML12159A3552012-06-0808 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11203A0782011-07-13013 July 2011 Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6 LR-N11-0090, 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations2011-04-0808 April 2011 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations ML11061A0052011-03-30030 March 2011 Ncsa Hope Creek Observations Rev. 4 LR-N10-0355, Salem, EAL Technical Bases Supporting Documents2010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML1100602392010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML11263A0302010-09-20020 September 2010 E-mail with Attachment from B. Pham, NRR to L. Perkins, NRR, on Forward Salem/Hope Creek Chapter 5 SAMA Input ML11263A0282010-09-16016 September 2010 E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo LR-N10-0306, 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S2010-08-10010 August 2010 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S LR-N09-0206, Special Report - North Plant Vent Radiation Monitoring System (Rms)2009-08-24024 August 2009 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit2008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit ML0831008272008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0247, Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action2008-10-30030 October 2008 Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action ML0826005732008-09-0202 September 2008 NFS-0255, Revision 0, Hope Creek Generating Station - Initial Implementation of WCAP-15942-P-A (Formerly CENO-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement to CENP-287, Evaluation of Control Blade I ML0732300962007-11-0909 November 2007 Discharge Confirmation Report - Retraction of Reported Discharge to the Delaware River HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error2007-05-23023 May 2007 Notice of Noncompliance and Affirmative Defense of Laboratory Error LR-N07-0040, Special Report - North Plant Vent Radiation Monitoring System (Rms)2007-02-20020 February 2007 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N06-0401, Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models2006-09-28028 September 2006 Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. ML0622805562006-07-27027 July 2006 Groundwater Protection - Data Collection Questionnaire LR-N06-0216, Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report2006-05-0404 May 2006 Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report ML0607204372006-03-0707 March 2006 Redacted Response to Request for Information Regarding Executive Review Board Commitments; PSEG ML0606703012006-02-0707 February 2006 PSEG-News Document Detailing Chris Bakken Will Succeed Anderson as President and CNO of PSEG Nuclear ML0605801622006-02-0101 February 2006 Performance Themes for Use After Inspection Exits (Regarding Poor Equipment Reliability, Corrective Action Ineffectiveness) and Organizational Issues (Regarding Engineering, Maintenance & Work Control, Operations, and Licensing/Regulatory C ML0524901582005-08-31031 August 2005 Allegation Receipt Report Regarding Facility: Hope Creek ML0526302272005-08-23023 August 2005 Communication Plan & Notification Sequence Regarding Receipt & Docketing of PSEG Assessment Reports ML0531803762005-04-30030 April 2005 NEDO-33186, Revision 1, MELLLA Tracg Divom Evaluation for Hope Creek at Cppu Conditions. 2023-12-15
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 August 10, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK NUCLEAR GENERATING STATION, UNIT 1 - CLOSEOUT OF BULLETIN 2011-01, "MITIGATING STRATEGIES" (TAC NO. ME6440)
Dear Mr. Joyce:
On May 11, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin (BL) 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111250360), to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel.
The purpose of BL 2011-01 was to obtain a comprehensive verification that the licensee's mitigating strategies to maintain or restore core cooling, spent fuel cooling, and containment, following a large explosion or fire are in compliance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(hh)(2).
BL 2011-01 required two sets of responses pursuant to the provisions of 10 CFR 50.54(f).
Hope Creek Nuclear Generating Station, Unit 1 (Hope Creek), provided its responses to BL 2011-01 by letters dated June 9 and July 11, 2011 (ADAMS Accession Nos. ML111600253 and ML111930027, respectively). By letter dated November 14,2011 (ADAMS Accession No. ML113110248), the NRC staff sent the licensee a request for additional information (RAJ) regarding its July 11, 2011, response. The licensee responded to the RAI by letter dated December 12, 2011 (ADAMS Accession No. ML113470207).
The NRC staff has reviewed the information submitted by Hope Creek, and concludes that its response to BL 2011-01 is acceptable. As summarized in the enclosure, the NRC staff verified that the licensee provided the information requested in BL 2011-01.
If you have any questions, please contact me at (301) 415-3204 or via email at john.hughey@nrc.gov.
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John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
As stated cc: Distribution via Listserv
SUMMARY
OF NRC BULLETIN 2011-01 "MITIGATING STRATEGIES" RESPONSE REVIEW PSEG NUCLEAR LLC HOPE CREEK NUCLEAR GENERATING STATION, UNIT 1 DOCKET NO. 50-354
1.0 INTRODUCTION
On May 11, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin (BL) 2011-01, "Mitigating Strategies," (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111250360) to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel.
BL 2011-01 required two sets of responses pursuant to the provisions of with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(f). The first set of responses were due 30 days after issuance of BL 2011-01.
By letter dated June 9, 2011 (ADAMS Accession No. ML111600253), Hope Creek Nuclear Generating Station (Hope Creek) provided its response to this first set of questions (first response). The second responses were due 60 days after issuance of the bulletin. By letter dated July 11, 2011 (ADAMS Accession No. ML111930027), Hope Creek provided its response to this second set of questions (second response). By letter dated November 14, 2011 (ADAMS Accession No. ML113110248), the NRC sent a request for additional information (RAI) on the second response. Hope Creek responded to the RAI by letter dated December 12, 2011 (ADAMS Accession No. ML113470207). As summarized below, the NRC staff has verified that Hope Creek provided the information requested in the bulletin.
2.0 BACKGROUND
On February 25, 2002, the NRC issued EA-02-026, "Order for Interim Safeguards and Security Compensatory Measures" (ICM Order). Section B.5.b of the ICM Order required licensees to develop specific guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities using readily available resources (equipment and personnel),
that can be effectively implemented under the circumstances associated with the loss of large areas of the plant due to explosions or fire.
By letter dated August 9, 2007 (ADAMS Accession No. ML072180018), the NRC staff issued its Safety Evaluation (SE) to document the final disposition of information submitted by Hope Creek regarding Section B.5.b of the ICM Order. Along with the SE, the NRC staff issued a conforming license condition to incorporate the B.5.b mitigating strategies into the licensing basis.
Enclosure
-2 On March 27, 2009, the NRC issued 10 CFR SO.S4(hh)(2) as a new rule, in order to capture the B.S.b mitigating strategies and related license conditions as regulatory requirements for both current and future licensees. At that time, licensee compliance with the conforming license conditions was sufficient to demonstrate compliance with 10 CFR SO.S4(hh)(2) (74 FR 13926);
therefore, no further actions were required on the part of current licensees.
3.0 TECHNICAL EVALUATION
3.1 30-Day Request In order to confirm continued compliance with 10 CFR SO.S4(hh)(2), BL 2011-01 requested that licensees address the following two questions within 30 days of issuing the bulletin:
- 1. Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
- 2. Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
The NRC staff reviewed Hope Creek's first response to determine if it had adequately addressed these questions, as summarized below.
3.1.1 Question 1: Availability and Capability of Equipment In its first response, Hope Creek confirmed that equipment it needs to execute the 10 CFR SO.S4(hh)(2) mitigating strategies is available and capable of performing its intended function. The NRC staff verified that this confirmation covered equipment needed for each of the three phases of the B.S.b mitigation strategies. Therefore, the NRC staff finds that Hope Creek has adequately responded to Question 1.
3.1.2 Question 2: Guidance and Strategies Can Be Executed In its first response, Hope Creek confirmed that the guidance and strategies it has implemented for 10 CFR SO.S4(hh)(2) are capable of being executed considering the current facility configuration, staffing levels, and staff's skills. Since Hope Creek has considered its current facility configuration, staffing levels, and staff's skills, and confirmed that it can execute its implemented guidance and strategies, the NRC staff finds that Hope Creek has adequately responded to Question 2.
3.2 60-Day Request BL 2011-01 required a response to the following five questions within 60 days of issuing the bulletin:
- 1. Describe in detail the maintenance of equipment procured to support the strategies and guidance required by 10 CFR SO.S4(hh)(2) in order to ensure that it is functional when needed.
-3
- 2. Describe in detail the testing of equipment procured to support the strategies and guidance required by 10 CFR 50.54(hh)(2) in order to ensure that it will function when needed.
- 3. Describe in detail the controls for ensuring that the equipment is available when needed.
- 4. Describe in detail how configuration and guidance management is ensured so that strategies remain feasible.
- 5. Describe in detail how you ensure availability of offsite support.
The NRC staff reviewed Hope Creek's submittals to determine if it had adequately addressed these questions, as summarized below. The NRC staff also reviewed the August 9,2007, SE to determine what equipment, training, and offsite resources at Hope Creek were relied upon by NRC staff to conclude that Hope Creek's actions would ensure compliance with Section B.5.b of the ICM Order and the conforming license condition.
3.2.1 Questions 1 and 2: Maintenance and Testing of Equipment Questions 1 and 2 of the 60-day request required licensees to describe in detail the maintenance and testing of equipment procured to support the strategies and guidance required by 10 CFR 50.54(hh)(2), in order to ensure that it is functional when needed. In its second response, Hope Creek listed the equipment used to support the 10 CFR 50.54(hh)(2) mitigating strategies which receives maintenance or testing. For each item, Hope Creek described the maintenance and testing performed, including the frequency and basis for the maintenance or testing activity.
The NRC staff verified that Hope Creek listed equipment that typically requires maintenance or testing which was relied upon to make conclusions in the SE or commonly needed to implement the mitigating strategies. In its second response, Hope Creek stated that the fire truck, portable pump, portable power supplies, hoses, and communications equipment receive maintenance or testing. Hope Creek did not identify maintenance or testing of monitor nozzles, spray nozzles, or similar devices in its second response. In its RAI response, Hope Creek stated that its refuel floor monitor nozzle, portable spray nozzles, and fire truck mounted spray nozzle do not receive periodic maintenance or testing, but are included in the inventory. The monitor nozzle was tested prior to installation. In its RAI response, Hope Creek described how it ensures there is sufficient fuel for the portable pump. Hope Creek also identified other items that support the mitigating strategies that receive maintenance or testing.
The NRC staff verified that Hope Creek described the process used for corrective actions and listed the testing performed to ensure that the strategies were initially feasible. Hope Creek stated in its second response that its corrective action program is used to document equipment failure, establish priorities, and perform trending.
Based upon the information above, the NRC staff finds that Hope Creek has provided the information requested by Questions 1 and 2.
-4 3.2.2 Question 3: Controls on Equipment Question 3 of the 50-day request required licensees to describe in detail the controls on equipment, such as inventory requirements, to ensure that the equipment is available when needed. A list of inventory deficiencies and associated corrective actions to prevent loss was also requested.
The NRC staff verified that Hope Creek described its process for ensuring that B.S.b equipment will be available when needed. In its second response, Hope Creek identified equipment included in its inventory, the inventory frequency, and storage requirements. Hope Creek indicated that its inventory verifies that the equipment listed is available. Hope Creek stated that at the time of its second response, there were no outstanding inventory deficiencies that would render the strategies not viable.
The NRC staff verified that Hope Creek inventoried equipment which was relied upon to make conclusions in the SE or commonly needed to implement the mitigating strategies. In its second response, Hope Creek stated that procured non-permanently installed B.S.b equipment is inventoried at least annually in accordance with station procedures. The second response specifically stated that the following items are included in the inventory: portable pump; fire truck; portable power supplies; hoses; communications equipment; nozzles; and adapters.
Hope Creek also identified other items that support the mitigating strategies that are inventoried.
Based upon the information above, the NRC staff finds that Hope Creek has provided the information requested by Question 3.
3.2.3 Question 4: Configuration and Guidance Management Question 4 of the 50-day request required licensees to describe in detail how configuration and guidance management is assured so that the strategies remain feasible.
The NRC staff verified that Hope Creek described its measures to evaluate plant configuration changes for their effects on the mitigating strategies and to ensure its procedures are current.
In its second response, Hope Creek stated that plant configuration changes are procedurally evaluated against the licensing basis, which includes the B.S.b mitigating strategies. Hope Creek stated that the design change process requires a review of affected procedures and guidelines and that guideline changes are validated to ensure that the B.S.b mitigating strategies remain viable.
The NRC staff verified that Hope Creek described measures it has taken to validate the procedures or guidelines developed to support the mitigating strategies. In its second response, Hope Creek identified testing in response to Question 2 that demonstrated the ability to execute some strategies. Hope Creek also stated that, "Initially, mitigating strategies were validated by walkdowns, engineering evaluations and/or table top reviews," and they were similarly revalidated in 2011.
The NRC staff verified that Hope Creek described the training program implemented in support of the mitigating strategies and how its effectiveness is evaluated. In its second response, Hope Creek identified the training provided to its operations personnel, emergency response
-5 organization, and fire brigade. Hope Creek also identified the frequency with which each type of training is provided and the methods for evaluating the training.
Based upon the information above, the NRC staff finds that Hope Creek has provided the information requested by Question 4.
3.2.4 Question 5: Offsite Support Question 5 of the SO-day request required licensees to describe in detail how offsite support availability is assured.
The NRC staff verified that Hope Creek listed the offsite organizations it relies upon for emergency response, including a description of agreements and related training. The NRC staff compared the list of offsite organizations that Hope Creek provided in its second response with the information relied upon to make conclusions in the SE. Hope Creek stated that it maintains a memorandum of understanding with these offsite organizations, which are reviewed at least biennially, and that these agreements were current at the time of its second response. Hope Creek also described the training and site familiarization it provides to these offsite organizations. Hope Creek stated that it reviewed its corrective action program back to 2008 and found no issues involving lapsed agreements related to offsite support for B.5.b events.
Based upon the information above, the NRC staff finds that Hope Creek has provided the information requested by Question 5.
4.0 CONCLUSION
As described above, the NRC staff has verified that Hope Creek has provided the information requested in Bulletin 2011-01. Specifically, Hope Creek responded to each of the questions in BL 2011-01, as requested. The NRC staff concludes that Hope Creek has completed all of the requirements of BL 2011-01 and no further information or actions under BL 2011-01 are needed.
, ML111600253 and ML111930027, respectively), By letter dated November 14, 2011 (ADAMS Accession No, ML113110248), the NRC staff sent the licensee a request for additional information (RAI) regarding its July 11, 2011, response. The licensee responded to the RAI by letter dated December 12, 2011 (ADAMS Accession No. ML113470207),
The NRC staff has reviewed the information submitted by Hope Creek, and concludes that its response to BL 2011-01 is acceptable, As summarized in the enclosure, the NRC staff verified that the licensee provided the information requested in BL 2011-01.
If you have any questions, please contact me at (301) 415-3204 or via email at john. hughey@nrc,gov.
Sincerely, Ira!
John D, Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No, 50-354
Enclosure:
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