Success/simplicity/safety/savings: SI/trip reduction at Indian point 2
In the 1980s, Consolidated Edison embarked on a unique, ambitious program of safety injection (SI)/trip reduction for its Indian Point Unit 2, four-loop Westinghouse 2758-MW (thermal), pressurized water reactor. The program had the following criteria: 1. Each SI/trip reduction modification should successfully eliminate a majority of unnecessary SI/trips of a specific type. 2. The hardware changes must be simple, having a minimum effect on operations, testing, and maintenance, and be cost-effective. 3. The modifications must retain a significant degree of safety margin, and where possible, be done under 10CFR50.59. Four specific SI/trip classes have been addressed. They are loss-of-feedwater trips, direct reactor trips on turbine generator trips, spurious SI/trips involving high steam flow, and trips following transients resulting from turbine runbacks. Significant results of the program, which involved new solutions to common industry problems, are described. The modifications involved simple schemes and were easily installed at a reasonable cost. Most were done with only one technical specification change required. Based on recent operational data and past trip experience, it is estimated that two to three reactor trips and/or SIs will be avoided per year.
- OSTI ID:
- 5497253
- Report Number(s):
- CONF-881011-; CODEN: TANSA; TRN: 89-030958
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC (USA), 30 Oct - 4 Nov 1988; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
INDIAN POINT-2 REACTOR
REACTOR SAFETY
REACTOR OPERATION
OPTIMIZATION
SAFETY INJECTION
REDUCTION
CALIBRATION
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
ECONOMICS
ENGINEERED SAFETY SYSTEMS
EPRI
FEEDWATER
FLOW RATE
LOSS OF COOLANT
MODIFICATIONS
PUMPS
REACTOR INSTRUMENTATION
REACTOR MAINTENANCE
REACTOR OPERATORS
ROD DROP ACCIDENTS
STEAM SYSTEMS
TESTING
TRANSIENTS
ACCIDENTS
CHEMICAL REACTIONS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
MAINTENANCE
OPERATION
OXYGEN COMPOUNDS
PERSONNEL
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled