Skip to main content

To present to stakeholders the result of NRC Research on SOARCA using Sequoyah Ice Condenser Containment Design

Meeting Details

Category 3
Date
April 20, 2016
Time
6:30 pm–8:00 pm EDT
Location
TVA Sequoyah Nuclear Training Building

2600 Igou Ferry Rd, Auditorium
Soddy Daisy, TN

Agenda
Meeting Info

Purpose

To present to stakeholders the result of NRC Research on SOARCA using Sequoyah Ice Condenser Containment Design

Docket

05000327 - Sequoyah 1
05000328 - Sequoyah 2

Documents

Document Title Description
ML16106A148 State-of-the-Art Reactor Consequence Analyses (SOARCA) Public Meeting Slides - April 2016
ML16109A309 04/20/2016 NRC Research: Sequoyah State-of-the-Art Reactor Consequence Analyses (SOARCA)
ML16083A086 Modeling Potential Reactor Accident Consequences (Brochure).
ML16096A374 State-of-the-Art Reactor Consequence Analyses (SOARCA) Project - Sequoyah Integrated Deterministic and Uncertainty Analyses (Draft Technical Report).

Participants

Office of Nuclear Reactor Regulation
Office of Nuclear Regulatory Research

External Participants

Tennessee Valley Authority
et al
Mike McBrearty
Andy Hon
Jonathan Barr
Patricia Santiago

Contact

Andy Hon

(301) 415-8480

Jonathan Barr

(301) 415-1089

Page Last Reviewed/Updated Monday, April 18, 2016