Criterion 18—Inspection and testing of electric power systems. Criterion 28—Reactivity limits. The design requirements for your project will differ from those of anyone else, because yours will apply to your specific problem statement and the product, system, or experience that you are designing. General Design Requirements Of R.C.C Structure: An efficient design of a reinforced concrete structure requires that the materials be economically selected, proportioned and arranged to carry the required loads without developing stresses which are in excess of the allowable working stresses. Weight Density Melting, boiling point Color Transparency Reflectance Surface texture (polished, rough) Elasticity Hardness Ductility (ability to be drawn into a wire) Magnetic properties Electrical properties (resistance, impedance, etc.) Criterion 52—Capability for containment leakage rate testing. Criterion 4—Environmental and dynamic effects design bases. ), (3) Consideration of the type, size, and orientation of possible breaks in components of the reactor coolant pressure boundary in determining design requirements to suitably protect against postulated loss-of-coolant accidents. This is the right to time to sit … (1) material properties, (2) the effects of irradiation on material properties, (3) residual, steady state and transient stresses, and (4) size of flaws. Under the provisions of § 50.34, an application for a construction permit must include the principal design criteria for a proposed facility. Criterion 55—Reactor coolant pressure boundary penetrating containment. PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION, Subchapter C. HAZARDOUS MATERIALS REGULATIONS, Part 173. The reactor core and associated coolant, control, and protection systems shall be designed to assure that power oscillations which can result in conditions exceeding specified acceptable fuel design limits are not possible or can be reliably and readily detected and suppressed. Criterion 27—Combined reactivity control systems capability. Criterion 25—Protection system requirements for reactivity control malfunctions. Means shall be provided for monitoring the reactor containment atmosphere, spaces containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents. Here is a more complete list of Design Requirement Examples. Criterion 50—Containment design basis. Criterion 26—Reactivity control system redundancy and capability. The emergency core cooling system shall be designed to permit appropriate periodic inspection of important components, such as spray rings in the reactor pressure vessel, water injection nozzles, and piping, to assure the integrity and capability of the system. Criterion 5—Sharing of structures, systems, and components. Criterion 2—Design bases for protection against natural phenomena. Structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. The reactor core and associated coolant systems shall be designed so that in the power operating range the net effect of the prompt inherent nuclear feedback characteristics tends to compensate for a rapid increase in reactivity. Your requirements will be more specific and directly related to meeting the needs of your project's users. (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure. (1) The temperature of the accessible surfaces of the package will not exceed 50 °C (122 °F) at an ambient temperature of 38 °C (100 °F) with no account taken for insulation; (2) The integrity of containment will not be impaired if the package is exposed to ambient temperatures ranging from −40 °C (−40 °F) to + 55 °C (131 °F); and. The barge unloaders shall be electric powered,travelling gantry mounted portal with boom & traversing trolley and with Grab attachment and provision of lifting beams & lifting hooks of suitable capacity. Criterion 37—Testing of emergency core cooling system. Appropriate systems shall be provided in fuel storage and radioactive waste systems and associated handling areas (1) to detect conditions that may result in loss of residual heat removal capability and excessive radiation levels and (2) to initiate appropriate safety actions. In addition to the requirements of subparts A and B of this part, each package used for the shipment of Class 7 (radioactive) materials must be designed so that -. Criterion 63—Monitoring fuel and waste storage. In addition to the requirements of subparts A and B of this part, each package used for the shipment of Class 7 (radioactive) materials must be designed so that -. Isolation valves outside containment shall be located as close to containment as practical and upon loss of actuating power, automatic isolation valves shall be designed to take the position that provides greater safety. A system to transfer heat from structures, systems, and components important to safety, to an ultimate heat sink shall be provided. This margin shall reflect consideration of (1) the effects of potential energy sources which have not been included in the determination of the peak conditions, such as energy in steam generators and as required by § 50.44 energy from metal-water and other chemical reactions that may result from degradation but not total failure of emergency core cooling functioning, (2) the limited experience and experimental data available for defining accident phenomena and containment responses, and (3) the conservatism of the calculational model and input parameters. § 173.410 General design requirements. (See Criteria 22, 24, 26, and 29.). One of these circuits shall be designed to be available within a few seconds following a loss-of-coolant accident to assure that core cooling, containment integrity, and other vital safety functions are maintained. Loss of coolant accidents mean those postulated accidents that result from the loss of reactor coolant at a rate in excess of the capability of the reactor coolant makeup system from breaks in the reactor coolant pressure boundary, up to and including a break equivalent in size to the double-ended rupture of the largest pipe of the reactor coolant system.1, Single failure. (b) Each lifting attachment that is a structural part of the package must be designed with a minimum safety factor of three against yielding when used to lift the package in the intended manner, and it must be designed so that failure of any lifting attachment under excessive load would not impair the ability of the package to meet other requirements of this subpart. One of the best ways to identify the design requirements for your project is to use the concrete example of a similar, existing product. Criterion 36—Inspection of emergency core cooling system. A system to supply reactor coolant makeup for protection against small breaks in the reactor coolant pressure boundary shall be provided. Criterion 21—Protection system reliability and testability. Criterion 22—Protection system independence. Protection and Reactivity Control Systems. Each line that connects directly to the containment atmosphere and penetrates primary reactor containment shall be provided with containment isolation valves as follows, unless it can be demonstrated that the containment isolation provisions for a specific class of lines, such as instrument lines, are acceptable on some other defined basis: Isolation valves outside containment shall be located as close to the containment as practical and upon loss of actuating power, automatic isolation valves shall be designed to take the position that provides greater safety. There will be some water-cooled nuclear power plants for which the General Design Criteria are not sufficient and for which additional criteria must be identified and satisfied in the interest of public safety. Overall Requirements: Quality Standards and Records: 1: Design Bases for Protection Against Natural Phenomena: 2: Fire Protection: 3: Environmental and Dynamic Effects Design Bases: 4: Sharing of Structures, Systems, and Components: 5: II. Fluid and electric systems are considered to be designed against an assumed single failure if neither (1) a single failure of any active component (assuming passive components function properly) nor (2) a single failure of a passive component (assuming active components function properly), results in a loss of the capability of the system to perform its safety functions.2.
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