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Issue date | Title | Topic | |
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ML21180A417 | 22 June 2021 | PWR Owners Group, Table 1- Comments on the Draft Safety Evaluation (Dse) for PWROG-19047-P and PWROG-19047-NP | |
ML20203M160 | 20 July 2020 | VA 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 & Status | Anchor Darling |
ML16130A564 | 2 May 2016 | NRC Regulatory Issue Summary 2015-16 Planned Licensing Action Submittals | Open Phase Condition Fuel cladding |
ML16056A139 | 11 March 2016 | Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports | |
ML14307B707 | 10 December 2014 | Supplemental 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-T | Probabilistic Risk Assessment Fukushima Dai-Ichi |
ML13242A017 | 23 August 2013 | Flood Hazard Reevaluation Supplemental Response to March 12, 2012 Information Request Regarding Flooding Aspects of Recommendation 2.1 | Fukushima Dai-Ichi |
ML072820307 | 11 October 2007 | Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists | |
ML070860287 | 5 February 2007 | 8th Pinc Meeting Feb. 5-6, 2007, Proposed CRDM and Bmi Mockups Using Na 2 Nozzle 31 Results | |
ML070860274 | 5 February 2007 | 8th Pinc Meeting Feb. 5-6, 2007, DAG-01 Analysis Scheme for Pinc Round Robin Test | |
ML063320133 | 28 November 2006 | Population Impacts for ABWR, MCSS2 | Fatality |
ML063320130 | 28 November 2006 | Table 7-4: AP1000 Collapsed Plume Characterization Data, MACCS2 | |
ML070860208 | 25 October 2006 | 7th Pinc Meeting 10/25 - 27, 2006 TG-NDE Test Blocks for Pinc Round Robin | Dissimilar Metal Weld |
ML060950094 | 3 April 2006 | North 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 Power | Safe Shutdown High winds Probabilistic Risk Assessment Reserve Station Service Transformer Contingency analyzer Earthquake Maintenance Rule Program |
ML050180257 | 13 January 2005 | Stations 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. | |
ML042470019 | 24 August 2004 | Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical Report | Shutdown Margin Coatings Nondestructive Examination Temporary Modification |
ML021360024 | 14 May 2002 | ASME 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 | |
ML021220088 | 5 April 2002 | Attachment 5 - Table R - Relocated Specifications and Removed Details North Anna, Units 1 and 2, Amendments 231 and 212 | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Post Accident Monitoring Earthquake Offsite Circuit |
ML021220067 | 5 April 2002 | Attachment 4 - Table L - Less Restrictive Changes North Anna, Units 1 and 2, Amendmends 231 and 212 | Boric Acid Time of Discovery Shutdown Margin High Radiation Area Post Accident Monitoring Missed surveillance Recently irradiated fuel Offsite Circuit Fire Protection Program |
ML021220061 | 5 April 2002 | Attachment 3 - Table M - More Restrictive Changes North Anna, Units 1 and 2, Amendments 231 and 212 | Boric 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 |
ML021220053 | 5 April 2002 | Attachment 2 - Table a - Administrative Changes North Anna, Units 1 and 2, Amendments 231 and 212 | Time of Discovery Shutdown Margin High Radiation Area Ultimate heat sink Hydrostatic Missed surveillance Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit |
ML19093B020 | 22 February 1978 | Response 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... |