Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum
- comp.; Brookhaven National Lab., Upton, NY (United States)
Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulation Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. The questions are motivated by the demand to meet the General Design Criterion 12 in Appendix A of the Code of Federal Regulation 10CFR50, which requires that reactor power oscillations violating Technical Specifications be either impossible by design, or detected and suppressed. Ten of the fourteen questions address BWR stability issues in general and are dealt with in this paper. The other four questions address local, out-of-phase oscillations and matters of instrumentation; they fall outside the scope of the work reported here.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10162029
- Report Number(s):
- NUREG/CP-0119-Vol.3-Add.; CONF-911079-Vol.3-Add.; ON: TI92017176
- Resource Relation:
- Conference: 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting,Bethesda, MD (United States),28-30 Oct 1991; Other Information: PBD: Jun 1992
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
STABILITY
EXCURSIONS
LA SALLE COUNTY-2 REACTOR
SCRAM
REACTOR SAFETY
ATWS
FLUID FLOW
OSCILLATIONS
TRANSIENTS
FAILURE MODE ANALYSIS
220900
210100
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED