Published April 1998 | Version v1
Report Restricted

Simplified approach for estimating large early release frequency

Creators

  • 1. Brookhaven National Lab., Upton, NY (United States)
  • 2. Sandia National Labs., Albuquerque, NM (United States)

Description

The US Nuclear Regulatory Commission (NRC) Policy Statement related to Probabilistic Risk Analysis (PRA) encourages greater use of PRA techniques to improve safety decision-making and enhance regulatory efficiency. One activity in response to this policy statement is the use of PRA in support of decisions related to modifying a plant's current licensing basis (CLB). Risk metrics such as core damage frequency (CDF) and Large Early Release Frequency (LERF) are recommended for use in making risk-informed regulatory decisions and also for establishing acceptance guidelines. This paper describes a simplified approach for estimating LERF, and changes in LERF resulting from changes to a plant's CLB

Availability note (English)

Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS TI98005775; NTIS

Files

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
BNL-NUREG--64995

Conference

Title
International conference on probabilistic safety assessment and management (PSAM4)
Dates
13-18 Sep 1998
Place
New York, NY (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
30009178
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CALCULATION METHODS; CONTAINMENT SYSTEMS; FAILURE MODE ANALYSIS; FISSION PRODUCT RELEASE; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; RISK ASSESSMENT
Descriptors DEC
ACCIDENTS; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC02-98CH10886
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States)
Secondary number(s)
CONF-980907--