Aging study of boiling water reactor high pressure injection systems
Creators
- 1. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
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
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI95009514; NTIS; GPO.Files
26054887.pdf
Files
(7.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 110 p.
- Report number
- NUREG/CR--5462
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26054887
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGING; BWR TYPE REACTORS; HIGH PRESSURE COOLANT INJECTION; LOSS OF COOLANT; REACTOR PROTECTION SYSTEMS; RESEARCH PROGRAMS; US NRC
- Descriptors DEC
- ACCIDENTS; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-94ID13223
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- INEL--94/0090.