The design basis for a loss of coolant accident in nuclear power plants has previously been based on the assumption that the largest size coolant pipe instantaneously undergoes a double ended “guillotine” break (DEGB) and the resulting loss of water must be mitigated by an emergency core cooling system (ECCS) to maintain core cooling after shutdown. The U.S. Nuclear Regulatory Commission (NRC) is close to allowing a risk-informed design basis break size, called the Transition Break Size (TBS), to be used for LOCA break size assumptions for ECCS design. The TBS approach will require full safety redundancy for an ECCS system sized to handle a break of the next largest reactor coolant pipe size (rather than the largest reactor coolant pipe size), and it will allow relaxed system redundancy requirements for handling the largest pipe break size. The TBS will thereby reduce the cost of the safety-grade ECCS system in new plant designs and will increase operational flexibility in existing plants. The TBS approach is based on the results of NRC elicitation studies with piping experts regarding historical pipe performance and risk of sudden failure. The approach is non-deterministic and is a conceptual change from the largest-pipe-size break assumption. The conceptual discontinuity between deterministic and elicitation-based break size assumptions could be uncomfortable for those schooled in strictly deterministic accident analyses. In this paper we explore the “leak-before-break” (LBB) methodology as it applies to large pipe break analyses in nuclear piping systems, and show through examples that the elicitation-based TBS approach is indeed conservative when TBS results are compared with deterministic LBB evaluations of similar piping systems. Thus, LBB provides a deterministic means for showing defense in depth against LOCAs greater than the TBS break size.
Skip Nav Destination
ASME 2011 Pressure Vessels and Piping Conference
July 17–21, 2011
Baltimore, Maryland, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4451-9
PROCEEDINGS PAPER
Use of LBB Methodology to Support the Transition Break Size Concept
James E. Nestell,
James E. Nestell
MPR Associates, Inc., Alexandria, VA
Search for other works by this author on:
David W. Rackiewicz
David W. Rackiewicz
MPR Associates, Inc., Alexandria, VA
Search for other works by this author on:
James E. Nestell
MPR Associates, Inc., Alexandria, VA
David W. Rackiewicz
MPR Associates, Inc., Alexandria, VA
Paper No:
PVP2011-57680, pp. 47-56; 10 pages
Published Online:
May 21, 2012
Citation
Nestell, JE, & Rackiewicz, DW. "Use of LBB Methodology to Support the Transition Break Size Concept." Proceedings of the ASME 2011 Pressure Vessels and Piping Conference. Volume 1: Codes and Standards. Baltimore, Maryland, USA. July 17–21, 2011. pp. 47-56. ASME. https://doi.org/10.1115/PVP2011-57680
Download citation file:
13
Views
Related Proceedings Papers
Risk-Informed and Defense-in-Depth Oriented Plant Design Approach
ICONE20-POWER2012
Related Articles
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
ASME J of Nuclear Rad Sci (April,2018)
Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors
ASME J of Nuclear Rad Sci (October,2015)
Rupture Hardware Minimization in Pressurized Water Reactor
Piping
J. Pressure Vessel Technol (February,1989)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Introduction
Fundamentals of Nuclear Fuel
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)