Published April 1996 | Version v1
Report Metadata-only

Risk follow-up on technical specifications

Creators

  • 1. Vattenfall Ab, Stockholm (Sweden)

Description

The paper describes the use of PSA to evaluate the instantaneous risk that a NPP has been exposed to during a year. It also demonstrate how the PSA is used to evaluate Technical Specification aspects e.g. allowed outage time (AOT) and allowed combinations of unavailable systems. (author). 4 figs, 1 tab

Part of:
Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting
Imprint Pagination
321 p.
Journal Page Range
p. 203-210.
ISSN
1011-4289
Report number
IAEA-TECDOC--873

Conference

Title
Technical committee meeting on application and development of probabilistic safety assessment for nuclear power plant operations.
Dates
20-23 Sep 1993.
Place
Barcelona (Spain).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
27056797
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EVALUATION; FORSMARK-1 REACTOR; FORSMARK-2 REACTOR; FORSMARK-3 REACTOR; PROBABILISTIC ESTIMATION; RINGHALS-1 REACTOR; RINGHALS-2 REACTOR; RINGHALS-3 REACTOR; RINGHALS-4 REACTOR; RISK ASSESSMENT; SAFETY; SAFETY ANALYSIS; SPECIFICATIONS
Descriptors DEC
BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information