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Welcome to Wiki site! The goal of this site is to apply semantic elements to Nuclear information.

If you would like to discuss this site or if you have cool ideas please visit the Community page.

Number of Pages: 557,641

Generic Adams

An Adams import was set up so that new correspondence will be imported periodically. If we can add context then we could better organize the letters into relevant groups. Ie groups around project codes.


Plants undergo inspections by the NRC. A series of pages have been uploaded representing the findings that resulted from those inspections. This is a good data set because it helps show a practical interpretation of regulation. In other words, who knows what it really means but this is how it was done wrong.


One of the bigger events for a plant is a Scram. The occurrence of which are reported to the NRC via the ENS system. By extracting that information you can get lists of data. Please see the main page Scram.

 Start dateSiteScram
ENS 5507820 January 2021 23:22:00Saint LucieAutomatic Scram


Recently Mapping has been incorporated to the wiki. Mostly its about plant locations and can show corporate owner icons. It is feasible to overlay a set of data with locations (ie you can see where ENS occurred on a Map).

Loading map...

Emergency Notification System

First successfully integrated database is the Emergency Notification System. It is a database which holds all the short-term notifications made by nuclear power plants (10 CFR 50.72). If you visit the Emergency Notification System you can see how digitizing the ENS can lead to a variety of customized reports and notifications.

Enjoy --StriderTol (talk) 15:09, 14 July 2014 (EDT)

Since Yesterday: 01-19-2021

 SiteSystemEvent descriptionTopic
ENS 55078Saint LucieSteam Generator
Steam Bypass Control System
Main Condenser
On 1/20/2021 at 1822 EST, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a loss of Motor Control Center 2B2. The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Auxiliary feed-water automatically actuated on the 2A Steam Generator post trip. Current decay heat removal is the 2B main feedwater pump to both steam generators and the Steam Bypass Control System to the main condenser.

Unit 1 is not affected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B).

The NRC Resident Inspector has been notified.