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PNL Technical Review of Pressurized Thermal Shock Issues Supplement 1 [electronic resource] : Technical Critique of the NRC Near-Term Screening Criteria

Published
Richland, Wash. : Pacific Northwest National Laboratory (U.S.), 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Pacific Northwest National Laboratory (U.S.) and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Pacific Northwest Laboratory (PNL) provided a technical critique of the draft report, NRC Staff Evaluation of Pressurized Thermal Shock, dated September 13, 1982. This report provided the basis for the NRC near-term regulatory position on pressurized thermal shock {PTS) and recommended a generic screening criteria for welds in the vessel beltline region. The PNL staff concluded that the screening criteria were adequate to meet the intent of the NRC safety goal and to retain past predictions of vessel reliability. The conclusion was based on selecting the plant-specific nilductility transition reference temperature (RT{sub NDT}) in the conservative manner described within the staff report. Conservative and unconservative factors were mentioned throughout the NRC staff report. The PNL staff has listed these factors together with unknown (may be either conservative or unconservative) factors and estimated, where possible, the range in °F RT{sub NDT}. The unknown factors were so widespread that the PNL staff recommended that specific conservatisms not be reduced until the unknowns are further resolved.
Report Numbers
E 1.99:pnl-4327 supp 1
E 1.99: nureg/cr-2837
nureg/cr-2837
pnl-4327 supp 1
Subject(s)
Note
Published through SciTech Connect.
05/01/1983.
"pnl-4327 supp 1"
" nureg/cr-2837"
Stevens, D. L.; Simonen, F. A.; Pederson, L. T.; Apley, W. J.; Bian, S. H.; Pelto, P. J.; Simonen, E. P.
Office of Nuclear Reactor Regulation
Funding Information
DE-AC06-76RL01830
View MARC record | catkey: 14800587