Main Page

Welcome to www.kanterella.com 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: 1,061,260

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.

Findings

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.

Scrams

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.

Mapping

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...

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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: 11-19-2024

	Site	System	Event description	Topic
ENS 57431	Seabrook	Steam Generator Feedwater Decay Heat Removal	The following information was provided by the licensee via phone and email: At 1350 (EST) on 11/19/2024, with Unit 1 in mode 1 at 100% power, the reactor was manually tripped due to an automatic trip of the `B' main feedwater pump turbine. The reactor trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in mode 3. Decay heat removal is being accomplished by the steam dumps to the condenser. Emergency feedwater actuated due to low-low steam generator (water) level, as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC resident inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The cause of the 'B' main feedwater pump trip is under investigation. There was maintenance involving the 'B' main feedwater pump at the time of the scram.
ENS 57432	Seabrook	Steam Generator Feedwater Decay Heat Removal	The following information was provided by the licensee via phone and email: At 1350 (EST) on 11/19/2024, with Unit 1 in mode 1 at 100 percent power, the reactor was manually tripped due to an automatic trip of the `B' main feedwater pump turbine. The reactor trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in mode 3. Decay heat removal is being accomplished by the steam dumps to the condenser. Emergency feedwater actuated due to low-low steam generator level, as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC resident inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The cause of the 'B' main feedwater pump turbine trip is under investigation.