Published April 1991
| Version v1
Report
Development of technical specification surveillance requirements for Sizewell ''B'' power station
Description
The paper describes the adaptation of Standard Technical Specifications to the licensing requirements of the United Kingdom for the first PWR to be built by Nuclear Electric plc (formerly a part of Central Electricity Generating Board). The application of probabilistic methods in the design and safety analysis is described, and the decisions to be taken on the scope, structure and interdependence of the technical specifications for Sizewell ''B'' Power Station are assessed. (author). 1 tab
Additional details
Publishing Information
- Imprint Title
- Use of probabilistic safety assessment to evaluate nuclear power plant technical specifications
- Imprint Pagination
- 293 p.
- Journal Page Range
- p. 219-223.
- Report number
- IAEA-TECDOC--599
Conference
- Title
- Technical committee meeting on the use of probabilistic safety assessment to evaluate nuclear power plant technical specifications.
- Dates
- 18-22 Jun 1990.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22081120
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- INSPECTION; PROBABILISTIC ESTIMATION; REACTOR LICENSING; SAFETY ANALYSIS; SIZEWELL-B REACTOR; SPECIFICATIONS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; LICENSING; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS