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 Issue dateTitleTopic
ML21081A19230 June 2021Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code AssessmentAnticipated operational occurrence
Nondestructive Examination
Exemption Request
Tristructural Isotropic
2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval29 June 2021Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth IntervalVT-2
ML21145A00428 June 2021Request for Withholding Information from Public Disclosure
ML21179C06028 June 2021Presentation - Scale/Melcor non-LWR Source Term Demonstration Project - Heat Pipe ReactorProbabilistic Risk Assessment
Fuel cladding
1CAN062102, Cycle 30 Core Operating Limits Report (COLR) Revision 125 June 2021Cycle 30 Core Operating Limits Report (COLR) Revision 1Shutdown Margin
ML21179A00425 June 2021NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69
ML21179A00525 June 2021NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69
ML21174A03422 June 2021NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions
0CAN062101, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling15 June 2021Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling
ML21158A2238 June 2021Meeting Summary for Ticap Workshop 3Probabilistic Risk Assessment
Maintenance Rule Program
ML21158A3007 June 2021Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XIIncorporated by reference
1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors26 May 2021Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ReactorsHot Short
Safe Shutdown
High winds
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
Incorporated by reference
FLEX
Fukushima Dai-Ichi
Tornado Missile Protection
Large early release frequency
Flooding Focused Evaluation
Fire Protection Program
Very Early Warning Fire Detection
2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors26 May 2021Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ReactorsHot Short
Safe Shutdown
High winds
Ultimate heat sink
Fire Barrier
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Incorporated by reference
FLEX
Fukushima Dai-Ichi
Tornado Missile Protection
Large early release frequency
Flooding Focused Evaluation
Fire Protection Program
0CAN052103, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency .25 May 2021Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency .
2CAN052103, Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)24 May 2021Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)Surveillance Frequency Control Program
Offsite Circuit
ML21140A38924 May 2021Riv Column 1 EOC 2020 Public Meeting SummaryCoronavirus
COVID-19
ML21141A18221 May 2021Closed Teleconference with Entergy Operations, Inc. Concerning Proposed Alternative to Allow Use of a Carbon Fiber Reinforced Polymer Composite System at Arkansas Nuclear One, Units 1 and 2
ML21118B03919 May 2021Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel CodeNon-Destructive Examination
Probabilistic Risk Assessment
ML21132A27919 May 2021Request for Approval of Change to the Entergy Quality Assurance Program Manual
IR 05000368/202130117 May 2021NRC Examination Report 05000368/2021301Job Performance Measure
ML21132A29514 May 2021Summary of Public Meeting to Discuss Technology Inclusive Content of Application ProjectProbabilistic Risk Assessment
Maintenance Rule Program
0CAN052101, Annual Radiological Environmental Operating Report for 202013 May 2021Annual Radiological Environmental Operating Report for 2020Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Chernobyl
ML21133A29813 May 2021Arkansas - Control Point Hazard
1CAN052104, Notification of Deviation from Materials Reliability Program (MRP) 2019-00811 May 2021Notification of Deviation from Materials Reliability Program (MRP) 2019-008Weld Overlay
0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes10 May 2021Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes
IR 05000313/20210016 May 2021Integrated Inspection Report 05000313/2021001 and 05000368/2021001Enforcement Discretion
Temporary Modification
Functionality Assessment
FLEX
Significance Determination Process
Operability Determination
Coronavirus
COVID-19
Fire Protection Program
Power change
Siren
ML21117A0265 May 2021Summary of Teleconference with Entergy Operations, Inc. to Discuss Forthcoming LAR Concerning Reactor Coolant System Primary Activity and Primary-to-Secondary Leak Rate
ML21099A0814 May 2021Cover Letter - NRC Feedback on Terrapower Advanced Sfr Fuel Assembly Qualification Plan
Press Release-IV-21-005, NRC to Hold Virtual Meeting to Discuss 2020 Performance of 10 Region IV Nuclear Power Plants30 April 2021Press Release-IV-21-005: NRC to Hold Virtual Meeting to Discuss 2020 Performance of 10 Region IV Nuclear Power Plants
0CAN042105, Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description30 April 2021Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual DescriptionCyber Security
PMNS20210563, Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek29 April 2021Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek
ML21127A16628 April 2021Alert and Notification System Design ReportHigh winds
Cyber Security
Inadvertent Siren Activation
1CAN042102, Relief Request ANO1-ISI-02628 April 2021Relief Request ANO1-ISI-026
0CAN042104, Emergency Plan and Alert and Notification System (ANS) Design Report28 April 2021Emergency Plan and Alert and Notification System (ANS) Design Report
ML21116A10926 April 2021NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping
0CAN042102, Radioactive Effluent Release Report for 202021 April 2021Radioactive Effluent Release Report for 2020Time of Discovery
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Tritium
0CAN042103, Annual Occupational Radiation Exposure Report21 April 2021Annual Occupational Radiation Exposure Report
1CAN042101, Cycle 30 Core Operating Limits Report (COLR)21 April 2021Cycle 30 Core Operating Limits Report (COLR)Shutdown Margin
ML21109A24319 April 2021Arkansan Nuclear One, Unit 1 - Notification of Inspection (NRC Inspection Report 05000313/2021003) and Request for InformationJob Performance Measure
ML21106A15116 April 2021and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations
ML21088A43314 April 2021Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing DefinitionAnticipated operational occurrence
ML21095A31613 April 2021ANO 2021402-Non SGI RclFitness for Duty
ML21105A0129 April 2021NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Adopt a Safety Function Determination ProgramOffsite Circuit
ML21137A2848 April 20211_AN2-2021-03 Draft OutlinesBoric Acid
Time Critical Operator Action
Offsite Circuit
ML21137A2908 April 20217_AN2-2021-03 Final OutlinesBoric Acid
Offsite Circuit
ML21137A2898 April 20216_AN2-2021-03 Operating Test Comments (Final)
ML21137A2858 April 20212_AN2-2021-03 Outline Comments
ML21137A2888 April 20215_AN2-2021-03 Draft Operating TestBoric Acid
Shutdown Margin
Grab sample
Hydrostatic
Job Performance Measure
Surveillance Frequency Control Program
Time Critical Operator Action
Deep Dose Equivalent
Pressure Boundary Leakage
Power change
Siren
Overexposure
ML21137A2778 April 2021Examination Outline Quality Checklist
ML21134A2418 April 20218_AN2-2021-03 Final Written ExamHot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Reactor Vessel Water Level
Loop seal
High Radiation Area
Grab sample
Stroke time
Post Accident Monitoring
Locked High Radiation Area
FLEX
Surveillance Frequency Control Program
Severe Accident Management Guideline
Earthquake
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
Power change
Downpower
Unidentified leakage