Back to Results
First PageMeta Content
Nuclear safety / Containment building / AP1000 / Nuclear safety in the United States / Pressurizer / Nuclear reactor / Evaluation / Sodium Reactor Experiment / Nuclear meltdown / Nuclear technology / Energy / Nuclear energy in the United States


Final Safety Evaluation Report - NUREG-1793, Supplement 2 - AP1000 Design Certification Amendment
Add to Reading List

Document Date: 2013-03-18 16:43:23

Open Document

File Size: 4,26 MB

Share Result on Facebook

Company

Westinghouse Electric Corporation / Control Rod Drive Systems / REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS / Control Room Habitability Systems / Reactivity Control Systems / Engineered Safety Features Actuation Systems / /

Facility

Reactor Coolant Pump Flywheel Integrity / Reactor Coolant Pump Assembly / Reactor Coolant System Component / Plant Design / Reactor Coolant / Reactor Vessel / Reactor Coolant Pressure Boundary Materials / Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington / Reactor Pressure Vessel Internals / Reactor Coolant Loop Analysis Methods / Reactor Vessel Materials / Reactor Internals / Reactor Vessel Insulation / Reactor Coolant Pressure Boundary / Reactor Materials / Reactor Internals Under Faulted Conditions / Reactor Trip System / /

Organization

U.S. Nuclear Regulatory Commission Washington / DC / Pump Assembly / New Reactor Licensing Office / Technical Support Center / U.S. Nuclear Regulatory Commission / /

Position

General / /

ProgrammingLanguage

DC / /

RadioStation

Core / /

SocialTag