A new feedwater control/isolation scheme to reduce steam generator thermal transients
Description
Con Edison has recently implemented a design modification for its Indian Point 2 (IP2) Westinghouse four-loop pressurized water reactor that delays feedwater isolation following a reactor trip and low T average. The purpose of the change is to reduce thermal transients to the steam generators by maintaining a flow of relatively hot main feedwater, rather than only cold auxiliary feedwater, until the steam generator levels recover. The goal is to reduce thermal stresses in the steam generator girth weld region. An additional benefit is reduction of thermal stresses to other components such as the feedwater nozzles. Based on engineering, operations, and safety considerations, this method was chosen over other potential solutions such as heating the auxiliary feedwater before it enters the steam generators. The project utilized a multidisciplinary approach and involved extensive design and analysis, testing, and operator training on the IP2 simulator
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 348.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038863
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; BYPASSES; CONTROL; CONTROL SYSTEMS; DESIGN; EFFICIENCY; ENGINEERED SAFETY SYSTEMS; FEEDWATER; HEAT TRANSFER; HYDRAULICS; IMPLEMENTATION; INDIAN POINT-2 REACTOR; LEVELS; MODIFICATIONS; PERFORMANCE TESTING; PRESSURIZERS; REACTOR LICENSING; REACTOR OPERATORS; REACTOR SAFETY; REACTOR SIMULATORS; SCRAM; STEADY-STATE CONDITIONS; STEAM GENERATORS; TEMPERATURE DEPENDENCE; THERMAL SHOCK; THERMAL STRESSES; TRAINING; TRANSIENTS; VALVES; WELDED JOINTS
- Descriptors DEC
- ANALOG SYSTEMS; AUXILIARY SYSTEMS; BOILERS; CONTROL EQUIPMENT; EDUCATION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FUNCTIONAL MODELS; HYDROGEN COMPOUNDS; JOINTS; LICENSING; OXYGEN COMPOUNDS; PERSONNEL; POWER REACTORS; PWR TYPE REACTORS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SIMULATORS; STRESSES; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.