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  2. APR-1400 - Wikipedia

    en.wikipedia.org/wiki/APR-1400

    APR-1400 design began in 1992 and was awarded certification by the Korean Institute of Nuclear Safety in May 2002. [3] The design certification application was submitted to the US Nuclear Regulatory Commission (NRC) in December 2014 and in March 2015, it was accepted for technical review to determine if the reactor design meets basic US safety requirements.

  3. File:NRC safety report - Diablo Canyon Nuclear Power Plant.pdf

    en.wikipedia.org/wiki/File:NRC_safety_report...

    English: NRC ISSUES FINAL SAFETY EVALUATION REPORT FOR DIABLO CANYON NUCLEAR POWER PLANT LICENSE RENEWAL The Nuclear Regulatory Commission has issued its safety evaluation report (SER) for the proposed renewal of the operating licenses for the Diablo Canyon Nuclear Power Plant, Units 1 and 2.

  4. Nuclear safety in the United States - Wikipedia

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

    In October 2011, the Nuclear Regulatory Commission (NRC) instructed agency staff to move forward with seven of the 12 safety recommendations put forward by the federal task force in July. The recommendations include "new standards aimed at strengthening operators' ability to deal with a complete loss of power, ensuring plants can withstand ...

  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. Generation III reactor - Wikipedia

    en.wikipedia.org/wiki/Generation_III_reactor

    Generation III+ reactors incorporate extra safety features to avoid the kind of disaster suffered at Fukushima in 2011. Generation III+ designs, passive safety, also known as passive cooling, requires no sustained operator action or electronic feedback to shut down the plant safely in the event of an emergency.

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