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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
THERMAL-HYDRAULIC PHENOMENA SUBCOMMITTEE MEETING
FEBRUARY 23, 1999
WESTINGHOUSE BE LBLOCA METHODOLOGY FOR UPI PLANTS
ROCKVILLE, MARYLAND

- TOPICAL AGENDA -



TOPIC PRESENTER TIME

1. Introduction G. Wallis 8:30 am 2. Overview of Experimental D. Bessette 8:45 - 10:15 am Results ** BREAK ** 10:15 - 10:30 am 3. Upper Plenum Pooling and M. Nissley (W) 10:30 - 12:00 noon Drain Distribution . Predictions of UPTF and CCTF Data . Sensitivity of Data Predictions to Injection Modeling . Comparisons of PWR Predictions with MPR/Siemens Estimates . Sensitivity of PWR Predictions to Injection Modeling ** LUNCH ** 12:00 - 1:00 pm 4. Assessment of Subcooled M. Nissley 1:00 - 2:00 pm CCFL Predictions . Comparisons with Data . Assessment of PWR Predictions Using Correlations 5. Reflooding of the Hot Assembly M. Nissley 2:00 - 3:30 pm in a UPI Plant . Experimental Evidence . Sensitivity of CCTF Predictions to Modeling . Details of Predicted PWR Flow Pattern . Sensitivity of PWR Results to Modeling ** BREAK ** 3:30 - 3:45 pm 6. Westinghouse Concluding M. Nissley 3:45 - 4:00 pm Remarks 7. Overview of NRR Safety F. Orr (NRR) 4:00 - 4:45 pm Evaluation for Westinghouse BE LBLOCA Methodology 8. Subcommittee Caucus and Adjourn 4:45 - 5:00 pm NOTE: Presentation time should not exceed 50 percent of the total time allocated for a specific item. The remaining 50 percent of the time is reserved for discussion. Number of copies of the presentation materials to be provided to the ACRS - 25. ACRS Contact: P. Boehnert PAB@NRC.GOV ACRS Senior Staff Engineer