Interfacing systems LOCAs (Loss of Coolant Accidents) at boiling water reactors

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The work presented in this paper was performed by Brookhaven National Laboratory (BNL) in support of Nuclear Regulatory Commission's (NRC) effort towards the resolution of Generic Issue 105 ''Interfacing System Loss of Coolant Accidents (LOCAs) at Boiling Water Reactors (BWRs).'' For BWRs, intersystem LOCA have typically either not been considered in probabilistic risk analyses, or if considered, were judged to contribute little to the risk estimates because of their perceived low frequency of occurrence. However, recent operating experience indicates that the pressure isolation valves (PIVs) in BWRs may not adequately protect against overpressurization of low pressure systems. The objective of ... continued below

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Pages: 7

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Chu, Tsong-Lun; Fitzpatrick, R. & Stoyanov, S. January 1, 1987.

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Description

The work presented in this paper was performed by Brookhaven National Laboratory (BNL) in support of Nuclear Regulatory Commission's (NRC) effort towards the resolution of Generic Issue 105 ''Interfacing System Loss of Coolant Accidents (LOCAs) at Boiling Water Reactors (BWRs).'' For BWRs, intersystem LOCA have typically either not been considered in probabilistic risk analyses, or if considered, were judged to contribute little to the risk estimates because of their perceived low frequency of occurrence. However, recent operating experience indicates that the pressure isolation valves (PIVs) in BWRs may not adequately protect against overpressurization of low pressure systems. The objective of this paper is to present the results of a study which analyzed interfacing system LOCA at several BWRs. The BWRs were selected to best represent a spectrum of BWRs in service using industry operating event experience and plant-specific information/configurations. The results presented here include some possible changes in test requirements/practices as well as an evaluation of their reduction potential in terms of core damage frequency (CDF).

Physical Description

Pages: 7

Notes

NTIS, PC A02/MF A01; 1.

Source

  • PSA 87: international topical meeting on probabilistic safety assessment and risk management, Zurich, Switzerland, 31 Aug 1987

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  • Other: DE87012493
  • Report No.: BNL-NUREG-39974
  • Report No.: CONF-870820-4
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 6128680
  • Archival Resource Key: ark:/67531/metadc1107620

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1987

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • April 23, 2018, 4:21 p.m.

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Chu, Tsong-Lun; Fitzpatrick, R. & Stoyanov, S. Interfacing systems LOCAs (Loss of Coolant Accidents) at boiling water reactors, article, January 1, 1987; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc1107620/: accessed April 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.