Published June 1991
| Version v1
Report
Improvements in main steam safety valve performance by root cause analysis and modifications
- 1. Kalsi Engineering, Inc., Sugar Land, TX (United States)
- 2. Toledo Edison Co., OH (United States)
Description
A summary of the root cause analysis of main steam safety valve (MSSV) vibration problems at the Davis-Besse Nuclear Power Station is presented along with modifications that have resulted in improved performance. The root cause was found to be flow-induced vibrations caused by acoustic resonance in the valve inlet nozzle and insufficient design margins in certain valve components. The highest level of flow-induced excitation was found to be at reduced power levels where acceptable performance should have been achieved, according to earlier guidelines that had been developed to avoid safety valve vibration problems. This paper presents analysis, test results, and alternative solutions for the MSSV problems
Additional details
Publishing Information
- Imprint Title
- Proceedings: EPRI power plant valves symposium 3
- Imprint Pagination
- 580 p.
- Journal Page Range
- p. 2A.67-2A.86.
- Report number
- EPRI-NP/GS--7339
Conference
- Title
- 3. Electric Power Research Institute (EPRI) power plant valves symposium.
- Dates
- 20-23 Aug 1990.
- Place
- Charlotte, NC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23028156
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AVAILABILITY; DAVIS BESSE-1 REACTOR; DAVIS BESSE-2 REACTOR; DAVIS BESSE-3 REACTOR; FAILURE MODE ANALYSIS; MAINTENANCE; MECHANICAL VIBRATIONS; MODIFICATIONS; NOZZLES; PERFORMANCE; PWR TYPE REACTORS; RELIEF VALVES; RESONANCE
- Descriptors DEC
- CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9008113--.