Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML23335A112 | 15 December 2023 | Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers | |
| ML23249A262 | 6 September 2023 | Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) | |
| RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies | 13 July 2022 | Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies | Earthquake Fire Protection Program |
| NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | 30 June 2022 | Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits | Mururoa |
| RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel | 20 January 2022 | Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel | Anticipated operational occurrence Post Accident Monitoring Fuel cladding |
| SVP-21-041, Regulatory Commitment Change Summary Report | 15 July 2021 | Regulatory Commitment Change Summary Report | |
| LR-N21-0007, Report of Changes, Tests, and Experiments | 28 January 2021 | Report of Changes, Tests, and Experiments | |
| RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | 4 January 2021 | Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping | Nondestructive Examination |
| ML20303A175 | 23 October 2020 | Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting | |
| SVP-20-074, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report | 8 October 2020 | Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report | Post Accident Monitoring |
| RS-20-086, Renewed Facility Operating License Nos. DPR-29 and DPR-30 | 24 September 2020 | Renewed Facility Operating License Nos. DPR-29 and DPR-30 | Exemption Request Pandemic Coronavirus COVID-19 |
| ML20121A133 | 3 March 2020 | Biological Opinion 2019 Annual Incidental Take Report | |
| ML19168A196 | 29 August 2019 | Staff Assessment of Flood Hazard Integrated Assessment | Safe Shutdown Unanalyzed Condition High winds Ultimate heat sink Hydrostatic FLEX Fukushima Dai-Ichi Backfit |
| RS-19-049, Submittal of 10 CFR 50.46 Annual Report | 2 May 2019 | Submittal of 10 CFR 50.46 Annual Report | |
| ML19064B370 | 5 March 2019 | Enclosure a - QDC-7500-M-2341, Revision 0, Quad Cities Units 1 & 2 Secondary Containment Drawdown Analysis. | Stroke time GOTHIC |
| ML19064B371 | 5 March 2019 | Enclosure B - QDC-0000-N-1481, Revision 3, Quad Cities Units 1 & 2 Post-LOCA Eab, LPZ, and CR Dose - AST Analysis. | |
| SVP-19-002, Submittal of 10 CFR 50.59, 10 CFR 72.48 Summary Report | 4 January 2019 | Submittal of 10 CFR 50.59, 10 CFR 72.48 Summary Report | |
| RS-18-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | 14 August 2018 | Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Safe Shutdown High winds Ultimate heat sink Mission time Time to boil Safe Shutdown Earthquake Hydrostatic Probabilistic Risk Assessment Emergency Lighting Functionality Assessment FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Time Critical Operator Action Battery sizing B.5.b Mitigating Strategies Flood Hazard Mitigation Strategies Assessment Hardened vent Fuel cladding |
| RS-18-089, 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 (EA-13-109) | 14 August 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 (EA-13-109) | High winds FLEX Tornado Generated Missile Design basis earthquake Spent Fuel Pool Instrumentation Severe Accident Management Guideline Containment Hardened Vent Battery sizing |
| 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 Conditions | 25 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 | High winds High Radiation Area Stroke time FLEX Tornado Missile Protection Design basis earthquake Foreign Material Exclusion Severe Accident Management Guideline Containment Hardened Vent Battery sizing Hardened vent |
| LR-N18-0057, Pressure and Temperature Limits Report, Revision 1 | 8 June 2018 | Pressure and Temperature Limits Report, Revision 1 | Pressure and Temperature Limits Report |
| RS-18-048, Submittal of 10 CFR 50.46 Annual Report Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. | 2 May 2018 | Submittal of 10 CFR 50.46 Annual Report Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. | |
| LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary | 9 November 2017 | License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary | Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding |
| SVP-17-046, Regulatory Commitment Change Summary Report | 6 July 2017 | Regulatory Commitment Change Summary Report | |
| 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 Report | 28 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 | Pressure and Temperature Limits Report |
| ML17188A267 | 31 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) | 31 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 6.9.1.1 | 9 February 2017 | Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 | Shutdown Margin |
| LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | 7 February 2017 | License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | Aging Management |
| ML17188A265 | 31 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 Ve | 31 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 Submittal | 29 December 2016 | Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | High winds Ultimate heat sink Hydrostatic FLEX Fukushima Dai-Ichi |
| ML16271A324 | 31 October 2016 | Technical Review Documentation for Flooding Hazard Reevaluation of Quad Cities Nuclear Power Station, Units 1 and 2 | Fukushima Dai-Ichi |
| ML16256A641 | 12 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. | 12 September 2016 | NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | |
| ML16256A640 | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
| ML16256A642 | 31 August 2016 | NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. | Safe Shutdown Earthquake Operating Basis Earthquake Cyber Security |
| LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | 31 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. | 31 August 2016 | NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. | Safe Shutdown Earthquake Operating Basis Earthquake Cyber Security |
| ML16256A643 | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
| LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents. | 18 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. | 31 May 2016 | GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. | Minimum Critical Power Ratio Fuel cladding |
| ML16049A609 | 29 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 | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
| RS-16-044, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | 19 February 2016 | High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
| ML15309A493 | 10 February 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force | Safe Shutdown Earthquake Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
| LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. | 30 September 2015 | NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. | |
| ML16256A644 | 30 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) | 30 September 2015 | NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) | |
| ML15251A384 | 31 August 2015 | Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) | Anticipated operational occurrence Finite Element Analysis |
| SVP-15-052, Submittal of Regulatory Commitment Change Summary Report | 8 July 2015 | Submittal of Regulatory Commitment Change Summary Report |