Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Load Reduction
Conference
·
OSTI ID:20995646
- Exelon Nuclear Engineering Department (United States)
The Quad Cities Units 1 and 2 have a history of steam line vibration issues. The implementation of an Extended Power Up-rate resulted in significant increases in steam line vibration as well as acoustic loading of the steam dryers, which led to equipment failures and fatigue cracking of the dryers. This paper discusses the results of extensive data collection on the Quad Cities Unit 2 replacement dryer and the Main Steam Lines. This data was taken with the intent of identifying acoustic sources in the steam system. Review of the data confirmed that vortex shedding coupled column resonance in the relief and safety valve stub pipes were the principal sources of large magnitude acoustic loads in the main steam system. Modifications were developed in sub-scale testing to alter the acoustic properties of the valve standpipes and add acoustic damping to the system. The modifications developed and installed consisted of acoustic side branches that were attached to the Electromatic Relief Valve (ERV) and Main Steam Safety Valve (MSSV) attachment pipes. Subsequent post-modification testing was performed in plant to confirm the effectiveness of the modifications. The modifications have been demonstrated to reduce vibration loads at full Extended Power Up-rate (EPU) conditions to levels below those at Original Licensed Thermal Power (OLTP). (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 20995646
- Country of Publication:
- United States
- Language:
- English
Similar Records
BWR Steam Dryer Alternating Stress Assessment Procedures
Acoustic Analysis for a Steam Dome and Pipings of a 1,100 MWe-Class Boiling Water Reactor
Test results employed by General Electric for boiling water reactor containment and vertical vent loads
Technical Report
·
Wed Nov 30 23:00:00 EST 2016
·
OSTI ID:1341604
Acoustic Analysis for a Steam Dome and Pipings of a 1,100 MWe-Class Boiling Water Reactor
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:21021144
Test results employed by General Electric for boiling water reactor containment and vertical vent loads
Technical Report
·
Wed Oct 01 00:00:00 EDT 1975
·
OSTI ID:4133903