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MN 17-016, 6/14/2017 - Notice of Category 3 Public Meeting - Annual Assessment Meeting for Indian Point Units 2 and 3
Press Release-I-16-013, NRC to Discuss Nine Mile Point Nuclear Plant Annual Assessment in Conjunction with May 18 Oswego, N.Y., Chamber of Commerce Meeting
Press Release-I-16-016, NRC to Hold Meeting with Exelon on May 26 in Stafford Township, N.J., Regarding Performance of Oyster Creek Nuclear Power Plant
Press Release-I-16-018, NRC to Hold Public Meeting on June 8 in Tarrytown, N.Y., Regarding Performance of Indian Point Nuclear Power Plant
Press Release-I-16-017, New NRC Inspector Assigned to Three Mile Island Nuclear Plant
MN 16-014, 4/13/2016 - Notice of Category 1 Public Meeting - Annual Assessment of Safety Performance at the Pilgrim Nuclear Power Station for 2015
Press Release-I-16-010, NRC to Hold Regulatory Performance Public Meeting Regarding Pilgrim Nuclear Power Plant on April 13 in Plymouth, Mass
Press Release-I-16-011, NRC to Hold Open House on April 21 to Discuss 2015 Performance of Calvert Cliffs Nuclear Power Plant
Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination
Press Release-I-18-002, NRC Assigns New Resident Inspector to FitzPatrick Nuclear Plant
Press Release-I-18-001, New NRC Inspector Named at Nine Mile Point Nuclear Plant
NL-17-159, Submittal of Relief Request IP2-ISI-RR-05 Alternative Examination Volume Required by Code Case N-729-4
LR-N17-0192, Anchor Darling Double Disc Gate Valve Information and Status
LR-N17-0191, No Active Safety Function Anchor Darling Double Disc Gate Valves
Press Release-I-14-039, NRC Issues White Inspection Finding for Millstone 3 Nuclear Plant; Level of Oversight to Be Increased
NL-14-145, Independent Spent Fuel Storage Installation (ISFSI) - Registration of a Spent Fuel Cask Use
NL-14-143, Reply to Request for Additional Information Regarding the License Renewal Application
LR-N14-0234, Request for Relief from American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code
NL-14-129, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50 Appendix H
NL-14-137, Reply to a Notice of Violation; EA-14-051 and EA-14-098
NL-14-140, Withdrawal of December 17, 2012 Coastal Zone Management Act Consistency Certification
Press Release-I-14-041, NRC Issues White Inspection Finding for Calvert Cliffs 2 Nuclear Plant; Level of Oversight to Be Increased
LR-N14-0230, Response to Request for Additional Information Re Core Operating Limits Report
RA-18-0002, H. 8. Robinson, Unit 2, Crystal River, Unit 3, Submittal of Onsite Property Insurance Coverage
NL-18-020, Core Operating Limits Report for Cycle 24
LR-N18-0020, Technical Specification 6.9.1.5.b, 2017 Annual Report of SRV Challenges
NL-18-005, Registration of Unit 2 Spent Fuel Cask Use Indian Point Nuclear Generating Unit No. 2
NL-17-156, Independent Spent Fuel Storage Installation (ISFSI) - Spent Fuel Cask Use Registration
NL-18-030, Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA)
NL-18-034, License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions
NL-18-039, LER 2018-001-00 for Indian Point, Unit 2 Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection
NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report
NL-18-063, Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.7
NL-18-044, Supplemental Information Regarding the Review of the License Renewal Application
NL-18-055, Initial Licensed Operator Examination Submittal
NL-18-021, Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability
NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability
NL-18-052, Relief Request IP3-ISI-RR-14, Proposed Alternative to ASME Code Case N-729-4 Examination Requirements
NL-18-048, Notice Regarding Proposed Fourth Amendment to Master Decommissioning Trust Agreement
NL-18-029, 2017 Annual Environmental Protection Plan Report
NL-18-011, Indian Point Energy Center - 2017 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
NL-18-008, Physical Security, Training and Qualification, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22
NL-17-144, Indian Point Nuclear Generating Unit 2, Proposed License Amendment Regarding Spent Fuel Storage
NL-18-045, Indian Point Nuclear Generating Unit 3 - Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years
Press Release-I-16-014, NRC Proposes $7,000 Civil Penalty for Violation at West Virginia Manufacturing Facility
Press Release-14-052, NRC Names Daniel H. Dorman as Region I Administrator
NL-18-065, Notice Regarding Proposed Fifth Amendment to Master Decommissioning Trust Agreement
Press Release-18-034, NRC Names David Lew Region I Administrator
LR-N18-0079, In-Service Inspection Activities - 90 Day Report Twenty First Refueling Outage
NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension
Press Release-I-07-048, - NRC Monitoring Alert at Nine Mile Point Unit 2
JAFP-07-0068, Response to May 1, 2007, Notice of Violation (NRC Investigation Report No. 1-2006-014) EA-07-029
NL-18-064, Revision to 2016 and 2017 Annual Fitness for Duty Program Performance Data
NL-18-082, Submittal of 2017 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
LR-N18-0124, Correction to In-Service Inspection Activities - 90 Day Report, Nineteenth Refueling Outage
BVY 18-038, Pre-Notice of Disbursement from Decommissioning Trust
LR-N19-0003, Report of Changes, Tests, and Experiments
NL-19-015, Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 15
RA-19-0185, Onsite Property Insurance Coverage
LR-N20-0011, In-Service Inspection Activities - 90 Day Report Twenty Second Refueling Outage
NL-19-021, Registration of Unit 3 Spent Fuel Cask Use
NL-19-022, Registration of Unit 3 Spent Fuel Cask Use
NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
NL-19-060, Technical Specification 5.6.8, Unit 3 Steam Generator Tube Inspection Report - Spring 2019 Refueling Outage (3R20)
NL-19-059, Registration of Unit 2 Spent Fuel Cask Use (2)
NL-19-062, Registration of Spent Fuel Cask Use
NL-19-070, Registration of Unit 2 Spent Fuel Cask Use
NL-19-090, Registration of Unit 2 Spent Fuel Cask Use
NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use
LR-N20-0012, Technical Specification 6.9.1.5.b: 2019 Annual Report of SRV Challenges
NL-20-039, (04/29/2020) E-mail from R. Gaston to R. Guzman, Exemption Request from Requirements of 10 CFR Part 73, Appendix B, Section VI, Subsection C.3.(l)(1)
LR-N21-0002, Technical Specification 6.9.1.5.b 2020 Annual Report of SRV Challenges
NL-21-021, Registration of Spent Fuel Cask Use
NL-21-027, Registration of Spent Fuel Cask Use
NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report
Press Release-I-21-002, NRC Names New Senior Resident Inspector at Indian Point Unit 3 Nuclear Power Plant
NL-21-028, 2020 Annual Environmental Protection Plan Report
LG-20-065, Owners Activity Report (OAR-1)
NL-20-036, 2019 Annual Environmental Protection Plan Report
LG-19-070, Owners Activity Report (OAR-1)
NL-19-037, 2018 Annual Environmental Protection Plan Report
05000247/LER-2018-003, For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap
05000286/LER-2018-003, Manual Reactor Trip Due to a Steam Leak on a High Pressure Feedwater Heater
05000286/LER-2018-002, Manual Reactor Shutdown Due to Weld Leak in Safety Injection System Tank
05000354/LER-2018-003-01, Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit
05000247/LER-2018-002, Manual Reactor Trip Due to Trip of Both Main Boiler Feedwater Pumps
05000247/LER-2018-001, Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection
05000286/LER-2018-001, Reactor Trip Due to Main Generator Loss of Excitation
05000286/LER-1917-004, Regarding Reactor Trip Due to Main Generator Loss of Field
NL-14-132, Response to 03/12/2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendations of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dia-ichi
Press Release-I-14-040, NRC Issues Security-related Inspection Finding for Limerick Nuclear Plant, Resulting in Increase in Agencys Oversight at Facility
MN 14-015, 6/4/2014 - Notice of Category 3 Public Meeting to Discuss Entergy Performance at Indian Point During Cy 2013
MN 16-015, Updated 6/8/2016 - Notice of Category 3 Public Meeting - Annual Assessment of Safety Performance for Indian Point Units 2 and 3 for 2015
LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports
Press Release-I-21-011, NRC Names New Resident Inspector for Nine Mile Point Nuclear Plant
OI 1-2015-005, Notice of Violation, NRC Office of Investigations Report No. 1-2015-005
OI 1-2009-042, NRC Office of Investigations Case No. 1-2009-042
OI 1-2009-025, NRC Office of Investigations Case No. 1-2009-025: Beaver Valley - Determine If Former Contractor Deliberately Withheld Info When Filling Out a PHQ
IA-19-033, Notice of Violation (NRC Investigation Report 1-2018-014)
IA-22-025, NRC Office of Investigations Report 1-2022-007 and Notice of Violation
IA-22-026, NRC Office of Investigations Report 1-2022-001 and Notice of Violation
IA-20-025, NRC Office of Investigation Report 1-2019-013 and Notice of Violation
IA-18-044, NRC Office of Investigations Report 1-2018-005 and Notice of Violation
OI 1-2009-028, NRC Office of Investigations Case No. I-2009-028 - Peach Bottom Letter
MN 07-006, Public Meeting with the Vermont State Legislature
BVY 19-024, Report of Investigation Pursuant to 10 CFR 20, Appendix G Vermont Yankee Nuclear Power Station, Docket No. 50-271, License No. DPR-28
BVY 19-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G Vermont Yankee Nuclear Power Station, Docket No. 50-271, License No. DPR-28
BVY 19-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G, Vermont Yankee Nuclear Power Station, Docket No. 50-271, License No. DPR-28
BVY 19-037, Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 19-043, Report of Investigation Pursuant to 10 CFR 20, Appendix G Vermont Yankee Nuclear Power Station, Docket No. 05000271, License No. DPR-28
BVY 19-029, Northstar Responses for Reports of Investigation Pursuant to 10 CFR 20, Appendix G Vermont Yankee Nuclear Power Station Docket No. 50-271, License No. DPR-28
L-21-078, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G
L-21-086, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G
BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G
BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G
NUREG/CR-6859, Use of the University of Marylands Letter Report, Thermal-hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment, as a Reference in Our NUREG/CR-6859, PRA Procedures and Uncertainty for PTS Analysis