Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

Conference · Mon Jun 01 00:00:00 EDT 1992

OSTI ID:5029812

Weiss, A J ^[1]

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1. 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: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 5029812
• 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
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
STABILITY
ATWS
EXCURSIONS
FAILURE MODE ANALYSIS
FLUID FLOW
LA SALLE COUNTY-2 REACTOR
OSCILLATIONS
REACTOR SAFETY
SCRAM
TRANSIENTS
ACCIDENTS
ENRICHED URANIUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWN
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled