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Title: Licensed reactor nuclear safety criteria applicable to DOE reactors

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.
Publication Date:
OSTI Identifier:
5873818
Report Number(s):
DOE/NE-0100T
ON: DE91010687; TRN: 91-015126
Resource Type:
Technical Report
Research Org:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (USA). Office of Nuclear Safety Policy and Standards
Sponsoring Org:
DOE; USDOE, Washington, DC (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NUCLEAR POWER PLANTS; REACTOR LICENSING; REACTORS; REACTOR SAFETY; REGULATIONS; US DOE; PROGRAM MANAGEMENT; CONSTRUCTION; DYNAMIC LOADS; ELECTRICAL EQUIPMENT; EMERGENCY PLANS; ENGINEERED SAFETY SYSTEMS; GEOLOGY; HEAT TRANSFER; HYDRAULICS; HYDROLOGY; MECHANICAL STRUCTURES; METEOROLOGY; PIPES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PUBLIC HEALTH; QUALITY ASSURANCE; RADIATION PROTECTION; RADIOACTIVE WASTE MANAGEMENT; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR DECOMMISSIONING; REACTOR INSTRUMENTATION; REACTOR MAINTENANCE; REACTOR OPERATION; SAFETY STANDARDS; SECONDARY COOLANT CIRCUITS; SEISMOLOGY; SITE SELECTION; SPECIFICATIONS; TRAINING; ACCIDENTS; CONTAINERS; CONTROL SYSTEMS; COOLING SYSTEMS; DECOMMISSIONING; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; FLUID MECHANICS; LICENSING; MAINTENANCE; MANAGEMENT; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SAFETY; STANDARDS; THERMAL POWER PLANTS; US ORGANIZATIONS; WASTE MANAGEMENT 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210700 -- Nuclear Power Plants-- Regulation & Licensing