Published April 1996 | Version v1
Report

Pilot study: Analysis of prescribed test intervals at Oskarshamn 2

Creators

  • 1. RELCON AB, Solna (Sweden)

Description

This report describes the used methods and the results from an analysis of test intervals carried out with the LPSA model for Oskarshamn 2 (LPSA-02). The analysis was made under a contract with OKG, department SR. The LPSA model is basically a normal PSA model, but with aim of calculating the current risk instead of average risk. The ability of the LPSA model to realistically calculate the influence of surveillance tests on risk is used to analyze test intervals. The primary purpose of this analysis is to demonstrate how LPSA can be used to analyze test intervals. This analysis is to be regarded as a first step in a more complete test interval analysis. The analysis aims at identifying test series that are more efficient than those prescribed in the current Technical Specifications. Test schemes have been identified, given by the scope, that are considerable more efficient than the existing test scheme prescribes by the Technical specifications. The results are tentative and generated within the scope and limitation given for this pilot study. The following continuation is recommended: Include Fire events; other hazard states than core damage should be analyzed; uncertainly analysis. (author). 5 refs, 3 tabs, 7 diagrams

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. 303-317.
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
27056798
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EVALUATION; L CODES; OKG-2 REACTOR; PROBABILISTIC ESTIMATION; RECOMMENDATIONS; RISK ASSESSMENT; SAFETY; SAFETY ANALYSIS
Descriptors DEC
BWR TYPE REACTORS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information