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 Issue dateTitleTopic
ML21180A41722 June 2021PWR Owners Group, Table 1- Comments on the Draft Safety Evaluation (Dse) for PWROG-19047-P and PWROG-19047-NP
ML20203M16020 July 2020VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & StatusAnchor Darling
ML16130A5642 May 2016NRC Regulatory Issue Summary 2015-16 Planned Licensing Action SubmittalsOpen Phase Condition
Fuel cladding
ML16056A13911 March 2016Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML14307B70710 December 2014Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-TProbabilistic Risk Assessment
Fukushima Dai-Ichi
ML13242A01723 August 2013Flood Hazard Reevaluation Supplemental Response to March 12, 2012 Information Request Regarding Flooding Aspects of Recommendation 2.1Fukushima Dai-Ichi
ML07282030711 October 2007Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0708602875 February 20078th Pinc Meeting Feb. 5-6, 2007, Proposed CRDM and Bmi Mockups Using Na 2 Nozzle 31 Results
ML0708602745 February 20078th Pinc Meeting Feb. 5-6, 2007, DAG-01 Analysis Scheme for Pinc Round Robin Test
ML06332013328 November 2006Population Impacts for ABWR, MCSS2Fatality
ML06332013028 November 2006Table 7-4: AP1000 Collapsed Plume Characterization Data, MACCS2
ML07086020825 October 20067th Pinc Meeting 10/25 - 27, 2006 TG-NDE Test Blocks for Pinc Round RobinDissimilar Metal Weld
ML0609500943 April 2006North Anna Units 1 and 2, and Surry Units 1 and 2, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite PowerSafe Shutdown
High winds
Probabilistic Risk Assessment
Reserve Station Service Transformer
Contingency analyzer
Earthquake
Maintenance Rule Program
ML05018025713 January 2005Stations Units 1 & 2, Millstone Power Station Units 2 & 3, Request for Approval of Appendix B of Topical Report DOM-NAF-2, Qualification of Westinghouse WRB-1 CHF Correlation in the Dominion VIPRE-D Computer Code.
ML04247001924 August 2004Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical ReportShutdown Margin
Coatings
Nondestructive Examination
Temporary Modification
ML02136002414 May 2002ASME Section XI Inservice Inspection (ISI) Program Relief Request Partial-1. Table - North Anna, Unit 2 - Reactor Vessel Outlet Nozzle to Shell Welds 10, 12 & 14
ML0212200885 April 2002Attachment 5 - Table R - Relocated Specifications and Removed Details North Anna, Units 1 and 2, Amendments 231 and 212Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Post Accident Monitoring
Earthquake
Offsite Circuit
ML0212200675 April 2002Attachment 4 - Table L - Less Restrictive Changes North Anna, Units 1 and 2, Amendmends 231 and 212Boric Acid
Time of Discovery
Shutdown Margin
High Radiation Area
Post Accident Monitoring
Missed surveillance
Recently irradiated fuel
Offsite Circuit
Fire Protection Program
ML0212200615 April 2002Attachment 3 - Table M - More Restrictive Changes North Anna, Units 1 and 2, Amendments 231 and 212Boric Acid
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Annual Radiological Environmental Operating Report
Annual Radiological Effluent Release Report
Deep Dose Equivalent
Recently irradiated fuel
Offsite Circuit
ML0212200535 April 2002Attachment 2 - Table a - Administrative Changes North Anna, Units 1 and 2, Amendments 231 and 212Time of Discovery
Shutdown Margin
High Radiation Area
Ultimate heat sink
Hydrostatic
Missed surveillance
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
ML19093B02022 February 1978Response to 02/02/78 Letter Possibility That Reactor Cavity Annulus Seal Ring or Associated Biological Shielding Could Become Missiles in Event of Loss of Coolant Accident Pipe...