Aging study of boiling water reactor high pressure injection systems

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The purpose of high pressure injection systems is to maintain an adequate coolant level in reactor pressure vessels, so that the fuel cladding temperature does not exceed 1,200{degrees}C (2,200{degrees}F), and to permit plant shutdown during a variety of design basis loss-of-coolant accidents. This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging degradation. Guidelines from the United States Nuclear ... continued below

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Medium: P; Size: 110 p.

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Conley, D.A.; Edson, J.L. & Fineman, C.F. March 1, 1995.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 16 times . More information about this report can be viewed below.

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Description

The purpose of high pressure injection systems is to maintain an adequate coolant level in reactor pressure vessels, so that the fuel cladding temperature does not exceed 1,200{degrees}C (2,200{degrees}F), and to permit plant shutdown during a variety of design basis loss-of-coolant accidents. This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging degradation. Guidelines from the United States Nuclear Regulatory Commission`s Nuclear Plant Aging Research Program were used in performing the aging study. Review and analysis of the failures reported in databases such as Nuclear Power Experience, Licensee Event Reports, and the Nuclear Plant Reliability Data System, along with plant-specific maintenance records databases, are included in this report to provide the information required to identify aging stressors, failure modes, and failure causes. Several probabilistic risk assessments were reviewed to identify risk-significant components in high pressure injection systems. Testing, maintenance, specific safety issues, and codes and standards are also discussed.

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Medium: P; Size: 110 p.

Notes

INIS; OSTI as TI95009514

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  • Other Information: PBD: Mar 1995

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  • Other: TI95009514
  • Report No.: NUREG/CR--5462
  • Report No.: INEL--94/0090
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/34240 | External Link
  • Office of Scientific & Technical Information Report Number: 34240
  • Archival Resource Key: ark:/67531/metadc688664

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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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  • March 1, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • June 25, 2018, 5:09 p.m.

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Conley, D.A.; Edson, J.L. & Fineman, C.F. Aging study of boiling water reactor high pressure injection systems, report, March 1, 1995; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc688664/: accessed December 11, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.