Identification of the operating crew's information needs for accident management

Conference · Fri Jan 01 00:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5579990

Nelson, W R; Hanson, D J; Ward, L W; Solberg, D E

While it would be very difficult to predetermine all of the actions required to mitigate the consequences of every potential severe accident for a nuclear power plant, development of additional guidance and training could improve the likelihood that the operating crew would implement effective sever-accident management measures. The US Nuclear Regulatory Commission (NRC) is conducting an Accident Management Research Program that emphasizes the application of severe-accident research results to enhance the capability of the plant operating crew to effectively manage severe accidents. One element of this program includes identification of the information needed by the operating crew in severe-accident situations. This paper discusses a method developed for identifying these information needs and its application. The methodology has been applied to a generic reactor design representing a PWR with a large dry containment. The information needs were identified by systematically determining what information is needed to assess the health of the critical functions, identify the presence of challenges, select strategies, and assess the effectiveness of these strategies. This method allows the systematic identification of information needs for a broad range of severe-accident scenarios and can be validated by exercising the functional models for any specific event sequence.

• OSTI ID: 5579990
• Report Number(s): CONF-881011-; CODEN: TANSA; TRN: 89-029075
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC (USA), 30 Oct - 4 Nov 1988; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR SAFETY
REACTOR ACCIDENTS
EMERGENCY PLANS
HUMAN FACTORS
AVAILABILITY
INFORMATION NEEDS
MANAGEMENT
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTOR OPERATORS
RELIABILITY
TRAINING
US NRC
ACCIDENTS
NATIONAL ORGANIZATIONS
OPERATION
PERSONNEL
REACTORS
SAFETY
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled