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Development of an improved HRA method: A technique for human error analysis (ATHEANA)

Conference ·
OSTI ID:269694
;  [1];  [2]
  1. Brookhaven National Lab., Upton, NY (United States)
  2. John Wreathall & Co., Dublin, OH (United States); and others
+ Show Author Affiliations

Probabilistic risk assessment (PRA) has become an increasingly important tool in the nuclear power industry, both for the Nuclear Regulatory Commission (NRC) and the operating utilities. The NRC recently published a final policy statement, SECY-95-126, encouraging the use of PRA in regulatory activities. Human reliability analysis (HRA), while a critical element of PRA, has limitations in the analysis of human actions in PRAs that have long been recognized as a constraint when using PRA. In fact, better integration of HRA into the PRA process has long been a NRC issue. Of particular concern, has been the omission of errors of commission - those errors that are associated with inappropriate interventions by operators with operating systems. To address these concerns, the NRC identified the need to develop an improved HRA method, so that human reliability can be better represented and integrated into PRA modeling and quantification.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
OSTI ID:
269694
Report Number(s):
NUREG/CP--0149-Vol.2; CONF-9510156--Vol.2; ON: TI96007985
Resource Relation:
23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995; Is Part Of Twenty-third water reactor safety information meeting: Volume 2, Human factors research; Advanced I and C hardware and software; Severe accident research; Probabilistic risk assessment topics; Individual plant examination: Proceedings; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 514 p.
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
HUMAN FACTORS
PERSONNEL
PROBABILISTIC ESTIMATION
RELIABILITY
WATER COOLED REACTORS