Developing and assessing accident management plans for nuclear power plants, Development process and criteria

Technical Report · Sat Aug 01 00:00:00 EDT 1992

OSTI ID:7269014

Hanson, D J; Blackman, H S; Meyer, O R; Ward, L W ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States)

This document is the first volume of a two-volume NUREG/CR. It describes a four-phase approach for developing criteria that can be used for assessing the adequacy of severe accident management plans for nuclear power plants. The general attributes of accident management plans (Phase 1) are identified, and a process for developing and implementing severe accident management plans (Phase 2) is described. This process is based on a prototype process described in NUREG/CR-5543. The prototype process was revised using results from an evaluation of this process (Phase 3), which is documented in Volume 2. General criteria for assessing the adequacy of accident management plans are also presented (Phase 4). These criteria were based on process specific criteria presented in Volume 2 and NUREG/CR-5543.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Idaho National Engineering Lab., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7269014
• Report Number(s): NUREG/CR-6009-Vol.1; EGG-2682-Vol.1; ON: TI92040699
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
MANAGEMENT
EMERGENCY PLANS
EQUIPMENT
EVALUATION
HUMAN FACTORS
PLANNING
REACTOR INSTRUMENTATION
REACTOR SAFETY
ACCIDENTS
NUCLEAR FACILITIES
POWER PLANTS
SAFETY
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
990100 - Management