Probabilistic safety assessment of unavailability of the manual shutdown system of Ling'ao phase II nuclear power plant
Creators
- 1. China Nuclear Power Engineering Company Ltd., Shanghai Branch, Shanghai (China)
Description
Distributed Control System (DCS) is implemented in Reactor Protection System (RPS) of Ling'ao Phase II. But manual reactor trip system, which is part of the RPS, is a conventional electric control system. Fault tree method is used in this article to evaluate failure rate of manual reactor trip system after the automatic means fail. Human reliability analysis is based on the Technique for Human Error Rate Prediction (THERP) methodology. For common cause failure analysis, Multiple Greek Letter (MGL) method is implemented. And general data of American NPP is used as data source. It shows that, the failure rate per demand of manual reactor trip system is 5.27 x 10-2. And operator failure to respond to the alarms, mis-reading neutron flux, omitting step to verify neutron flux increasing, selecting wrong control to scram the reactor, all these human errors contribute a lot to system failure. So operators should be well trained, thus can minimize the failure rate of manual reactor trip system. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 978-7-5022-4792-8
- Imprint Title
- Proceeding of the 1th science academic exchanges activity of China Guangdong Nuclear Power Engineering Co., Ltd.
- Imprint Pagination
- 191 p.
- Journal Page Range
- p. 38-42
Conference
- Title
- 1. science academic exchanges activity of China Guangdong Nuclear Power Engineering Co., Ltd.
- Dates
- Sep 2009
- Place
- Shenzhen, Guangdong (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43021280
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUGMENTATION; CHINA; CONTROL SYSTEMS; ERRORS; FAILURES; FAULT TREE ANALYSIS; FORECASTING; HUMAN FACTORS; MANUALS; NEUTRON FLUX; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; RELIABILITY; RISK ASSESSMENT; SCRAM
- Descriptors DEC
- ASIA; CALCULATION METHODS; DOCUMENT TYPES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; RADIATION FLUX; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 figs., 1 tab., 3 refs.