Operating plant safety analysis needs
Description
The primary objective for nuclear power station owners is to operate and manage their plants safely. However, there is also a need to provide economical electric power, which requires that the unit be operated as efficiently as possible, consistent with the safety requirements. The objectives cited above can be achieved through the identification and use of available margins inherent in the plant design. As a result of conservative licensing and analytical approaches taken in the past, many of these margins may be found in the safety analysis limits within which plants currently operate. Improvements in the accuracy of the safety analysis, and a more realistic treatment of plant initial and boundary conditions, can make this margin available for a variety of uses which enhance plant performance, help to reduce O and M costs, and may help to extend licensed operation. Opportunities for improvement exist in several areas in the accident analysis normally performed for Chapter 15 of the FSAR. For example, recent modifications to the ECCS rule, 10CFR50.46 and Appendix K, allow use of margins previously unavailable in the analysis of the Loss of Coolant Accident (LOCA). To take advantage of this regulatory change, new methods are being developed to analyze both the large and small break loss of coolant accident (LOCA). As this margin is used, enhancements in the analysis of other transients will become necessary. The paper discusses accident analysis methods, future development needs, and analysis margin utilization in specific accident scenarios
Additional details
Publishing Information
- Imprint Title
- Seventh international RETRAN conference: Proceedings
- Imprint Pagination
- 650 p.
- Journal Page Range
- p. 2.39-2.44.
- Report number
- EPRI-TR--100361
Conference
- Title
- 7. international RETRAN conference.
- Dates
- 15-18 Sep 1991.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24019553
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; BOUNDARY CONDITIONS; BWR TYPE REACTORS; DEPARTURE NUCLEATE BOILING; EFFICIENCY; EMERGENCY PLANS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; LOSS OF FLOW; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR KINETICS; REACTOR LICENSING; REACTOR OPERATORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; REGULATIONS; THREE-DIMENSIONAL CALCULATIONS; US NRC
- Descriptors DEC
- ACCIDENTS; BOILING; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; KINETICS; LAWS; LICENSING; NATIONAL ORGANIZATIONS; NUCLEATE BOILING; PERSONNEL; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9109388--.