Secondary water chemistry control at St. Lucie No. 1
Technical Report
·
OSTI ID:6606591
Plant design and operating philosophy relative to secondary cycle chemistry control at St. Lucie Nuclear Power Station Unit 1 were reviewed. St. Lucie 1 experienced moderate steam generator corrosion (tube denting) after only 17 months of commercial operation. Since the corrosion appeared related to the introduction of contaminants into the secondary cycle from intermittent condenser tube leakage, the condenser was retubed with titanium, and integrally grooved tubesheets were installed. Recently a new type of corrosive attack was found at the U-bend region of both steam generators. The precise nature and cause of this attack have not yet been determined.
- Research Organization:
- NWT Corp., San Jose, CA (USA)
- OSTI ID:
- 6606591
- Report Number(s):
- EPRI-NP-2706; ON: DE83900752
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
COOLING SYSTEMS
CORROSION
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
LUCIE-1 REACTOR
MATERIALS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTORS
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
COOLING SYSTEMS
CORROSION
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
LUCIE-1 REACTOR
MATERIALS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTORS
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS