Final report, BWR drywell debris transport Phenomena Identification and Ranking Tables (PIRTs)

Technical Report · Mon Sep 01 04:00:00 EDT 1997

DOI:https://doi.org/10.2172/573319· OSTI ID:573319

Wilson, G E ^[1]; Boyack, B E ^[2]; Leonard, M T; Williams, K A; Wolf, L T

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1. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
2. Los Alamos National Lab., NM (United States)

The Nuclear Regulatory Commission has issued a Regulatory Bulletin and accompanying Regulatory Guide (1.82, Rev. 2) which requires licensees of boiling water reactors to develop a specific plan of action (including hardware backfits, if necessary) to preclude the possibility of early emergency core cooling system strainer blockage following a postulated loss-of-coolant-accident. The postulated mechanism for strainer blockage is destruction of piping insulation in the vicinity of the break and subsequent transport of fragmented insulation to the wetwell. In the absence of more definitive information, the Regulatory Guide recommends that licensees assume a drywell debris transport fraction of 1.0. Accordingly, the Nuclear Regulatory Commission initiated research focused toward developing a technical basis to provide insights useful to regulatory oversight of licensee submittals associated with resolution of the postulated strainer blockage issue. Part of this program was directed towards experimental and analytical research leading to a more realistic specification of the debris transport through the drywell to the wetwell. To help focus this development into a cost effective effort, a panel, with broad based knowledge and experience, was formed to address the relative importance of the various phenomena that can be expected in plant response to postulated accidents that may produce strainer blockage. The resulting phenomena identification and ranking tables reported herein were used to help guide research. The phenomena occurring in boiling water reactors drywells was the specific focus of the panel, although supporting experimental data and calculations of debris transport fractions were considered.

• Research Organization: Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 573319
• Report Number(s): INEEL/EXT--97-00894; ON: DE98052254
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BLOWDOWN
BWR TYPE REACTORS
ECCS
FLOW BLOCKAGE
LOSS OF COOLANT
MASS TRANSFER
MITIGATION
PROGRESS REPORT
RECOMMENDATIONS
RESEARCH PROGRAMS