Published September 1989 | Version v1
Report

Use of reliability and risk standards as bases for acceptance in licensing and regulation of nuclear power plants

  • 1. Finnish Centre for Radiation and Nuclear Safety (STUK), Helsinki (Finland)

Description

The prevention and mitigation of accidents in PWR and BWR type reactor plants is essentially based on the sufficient operability of certain primary safety systems. To ensure sufficient reliability, the authority sets forth numerical reliability goal for the most important safety functions of new nuclear power plants. The unreliability of the function in question shall remain below this goal. To calculate the reliability of systems, one uses a data base which has been collected from the operating experiences of similar plants. If a data base of this kind is not available, a generic data base is utilized. However no fixed numerical acceptance standards are set forth in advance for the probabilities of a core melt, but the estimated probabilities are compared with the known probabilities of a core melt at other nuclear power plants. As concerns the operating plants it is defined in the Technical Specifications under what conditions the operation of the plant can be continued when faults have been detected in components important to safety. However, the Technical Specifications do not cover all situations in plant operation. Especially if there is a hidden potential fault discovered after the commissioning of the plant, for example an initiating event that may damage systems important to safety, the decision concerning the shutdown of the plant and the urgency of the repair must be made utilizing a probabilistic criteria. In cases like this, the authority requires that the power company estimate the annual risk of a core melt caused by the safety deficiency in question. The authority will perform an independent estimate and considers the shutdown of the plant and the urgency of the repair by comparing the risk of a core melt caused by the safety deficiency with the risk of a core melt estimated in connection with the PSA. 2 refs, 2 figs, 1 tab

Part of:
Status, experience and future prospects for the development of probabilistic safety criteria

Additional details

Publishing Information

Imprint Title
Status, experience and future prospects for the development of probabilistic safety criteria
Imprint Pagination
241 p.
Journal Page Range
p. 183-194.
Report number
IAEA-TECDOC--524

Conference

Title
Technical committee on status, experience and future prospects for the development of probabilistic safety criteria.
Dates
27-31 Jan 1986.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21028644
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LICENSING; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RADIATION PROTECTION; REACTOR SAFETY; REGULATIONS; RISK ASSESSMENT; SAFETY STANDARDS
Descriptors DEC
LAW; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS

Optional Information