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  • ANS 56.3 : 77(R1987)

    Withdrawn A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

    OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY

    Available format(s):  Hardcopy, PDF

    Withdrawn date:  23-07-2013

    Language(s):  English

    Published date:  12-01-2013

    Publisher:  American Nuclear Society

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    Abstract - (Show below) - (Hide below)

    Covers the interaction of those low pressure systems with the high pressure portions of the reactor coolant pressure boundary (RCPB) which, if assumed over-pressurized by the reactor coolant, could result in failure of the low pressure system and (1) the prevention of an orderly reactor shut-down or (2) the inability to maintain a safe shut-down condition assuming makeup is provided by normal makeup systems only or (3) the release of radioactive material at the site boundary exceeding 0.5 rem to the whole body or its equivalent to any part of the body. It also covers design and testing requirements for equipment, controls and instrumentation necessary for over-pressure protection of such low pressure systems.

    General Product Information - (Show below) - (Hide below)

    Document Type Standard
    Publisher American Nuclear Society
    Status Withdrawn

    Standards Referenced By This Book - (Show below) - (Hide below)

    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS

    Standards Referencing This Book - (Show below) - (Hide below)

    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
    IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
    IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
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