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AbstractAbstract
[en] Current Nuclear Regulatory Commission (NRC) Regulations and Guidelines were reviewed and those applicable to the functions of the passive heat removal systems were identified. A summary is provided of the applicable regulatory documents and the required system functional requirements stated in these documents for each of the passive heat removal systems. Based on a comparison of the regulatory requirements with the results of the performance assessments of the passive heat removal systems, it is concluded that each system will perform in accordance with the functional requirements with the following exception. With regard to the requirement for the passive residual heat removal system to achieve a cold shutdown temperature of 200F within a 36-hour period, the system performance assessments indicate that this requirement will not be met. The performance evaluations indicate that the reactor coolant system temperature will be approximately 330F at 36 hours after reactor shutdown. It is noted that Branch Technical Position RSB 5-1 states that plants which have residual heat systems that have the same design pressure as the reactor coolant system or which are located inside containment will be reviewed on a case-by-case basis. However, there is no indication at this time whether the performance capability of the passive heat removal system will be considered acceptable by the NRC. This is an issue which is being pursued by the advanced light water reactor pogram, in connection with developing the Requirements Document for the passive plant. The basic position to be taken is that the passive RHR system can maintain the reactor in a safe, stable state for at least 72 hours without any operator action and that only minimal action would be necessary to extend operation indefinitely. The paper identifies actions recommended to enhance likelihood for regulatory acceptance
Primary Subject
Source
Electric Power Research Inst., Palo Alto, CA (United States); MPR Associates, Inc., Washington, DC (United States); 71 p; Mar 1991; p. 6.1-6.6; Research Reports Center, PO Box 50490, Palo Alto, CA 94303
Record Type
Report
Report Number
Country of publication
AFTER-HEAT REMOVAL, CONTROL ROOMS, HYDROGEN, IN-SERVICE INSPECTION, PERFORMANCE, PRIMARY COOLANT CIRCUITS, PWR TYPE REACTORS, REACTOR CONTROL SYSTEMS, REACTOR LICENSING, REACTOR OPERATION, REACTOR OPERATORS, REACTOR SAFETY, REACTOR SHUTDOWN, REGULATIONS, SAFETY ENGINEERING, STANDARDIZATION, US NRC, VALVES
CONTROL EQUIPMENT, CONTROL SYSTEMS, COOLING SYSTEMS, ELEMENTS, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, INSPECTION, LAWS, LICENSING, NATIONAL ORGANIZATIONS, NONMETALS, OPERATION, PERSONNEL, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, REMOVAL, SAFETY, SHUTDOWN, THERMAL REACTORS, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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