Improved safety of the system 80+TM standard plants design through increased diversity and redundancy of safety systems
- 1. ABB Combustion Engineering, Windsor (United States)
Description
Safely systems in the System 80+TM Standard Plant are designed with more redundancy, diversity and simplicity than earlier nuclear power plant designs. These gains were accomplished by an evolutionary process that preserved the desirable and proven features in currently operating nuclear plants, while improving reliability and defense-in-depth. The System 80+ safety systems are the primary contributors to a core damage frequency that is more than 100 times lower than 1980's vintage U. S. designs, including the predecessor System 80R standard nuclear steam supply system (NSSS) design. The System 80+ design includes significant improvements to the safety injection system, emergency feedwater system, shutdown cooling system, containment spray system, reactor coolant gas vent system, and to their vital support systems. These improvements enhance performance for traditional design basis events and significantly reduce the probability of a severe accident. The System 80+ design also incorporates safety systems to mitigate a severe accident. The added systems include the rapid depressurization system, the in-containment refueling water storage tank, the cavity flooding system. These systems fully address the U. S. Nuclear Regulatory Commission's (US NRC) severe accident policy. The System 80+ safety systems are integrated with the System 80+ Nuclear Island (NI) design. The NI general arrangement provides quadrant separation of the safety systems for protection from fire and flooding, and large equipment pull spaces and lay down areas for maintenance. This paper will describe the System 80+ safety systems advanced design features, the improved accident prevention and mitigation capabilities, and startup, operating and maintenance benefits
Additional details
Publishing Information
- Publisher
- KAIF-KNS
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the 11th KAIF/KNS Annual Conference
- Imprint Pagination
- 864 p.
- Journal Page Range
- p. 415-431
Conference
- Title
- 11. KAIF/KNS Annual Conference
- Dates
- 11-12 Apr 1996
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 44076777
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLING SYSTEMS; DESIGN; ENGINEERED SAFETY SYSTEMS; MAINTENANCE; NUCLEAR POWER PLANTS; PERFORMANCE; PROBABILITY; REACTOR OPERATION; STEAM SYSTEMS
- Descriptors DEC
- ENERGY SYSTEMS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- Imprint:7 refs, 22 figs, 11 tabs