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  2. APR-1400 - Wikipedia

    en.wikipedia.org/wiki/APR-1400

    The first commercial APR-1400 reactors at Shin Kori were approved in September 2007, [12] with construction starting in October 2008 (Unit 3) and August 2009 (Unit 4). [3] [13] [14] Shin Kori-3 was initially scheduled to commence operation by the end of 2013, but the schedules for both Units 3 & 4 were delayed by approximately one year to replace safety-related control cabling, which had ...

  3. Nuclear emergency level classification responses - Wikipedia

    en.wikipedia.org/wiki/Nuclear_emergency_level...

    Nuclear power plants pose high risk to public health and safety if radiation is released into surrounding communities and areas. This nuclear emergency level classification response system was firstly developed by the US Nuclear Regulatory Commission to allow effective and urgent responses to ultimately control and minimise any detrimental effects that nuclear chemicals can have. [1]

  4. Nuclear safety in the United States - Wikipedia

    en.wikipedia.org/wiki/Nuclear_safety_in_the...

    Nuclear safety in the United States is governed by federal regulations issued by the Nuclear Regulatory Commission (NRC). The NRC regulates all nuclear plants and materials in the United States except for nuclear plants and materials controlled by the U.S. government, as well those powering naval vessels. [1] [2]

  5. WASH-1400 - Wikipedia

    en.wikipedia.org/wiki/WASH-1400

    WASH-1400, 'The Reactor Safety Study (later known as NUREG-75/014) was a report produced in 1975 for the Nuclear Regulatory Commission by a committee of specialists under Professor Norman Rasmussen. It "generated a storm of criticism in the years following its release". [ 1 ]

  6. NUREG-1150 - Wikipedia

    en.wikipedia.org/wiki/NUREG-1150

    NUREG-1150 "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants", published December 1990 by the Nuclear Regulatory Commission (NRC) is a follow-up to the WASH-1400 and CRAC-II safety studies that employs the methodology of plant-specific Probabilistic Risk Assessment (PRA).

  7. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    Because this includes cooling the systems that remove decay heat from both the primary system and the spent fuel rod cooling ponds, the ESWS is a safety-critical system. [7] Since the water is frequently drawn from an adjacent river, the sea, or other large body of water, the system can be fouled by seaweed, marine organisms, oil pollution, ice ...

  8. Office of Nuclear Reactor Regulation - Wikipedia

    en.wikipedia.org/wiki/Office_of_Nuclear_Reactor...

    The office should not be confused with the NRC's Nuclear Regulatory Research. The office's current director is William Dean. It has deputy directorates for two areas: (1) Reactor Safety Programs and (2) Engineering and Corporate Support. It has program management, policy development and analysis staff as well as an array of divisions.

  9. Nuclear Regulatory Commission - Wikipedia

    en.wikipedia.org/wiki/Nuclear_Regulatory_Commission

    The United States Nuclear Regulatory Commission (NRC) is an independent agency of the United States government tasked with protecting public health and safety related to nuclear energy. Established by the Energy Reorganization Act of 1974 , the NRC began operations on January 19, 1975, as one of two successor agencies to the United States ...