Automatic isolation of auxiliary feedwater
Creators
Description
Generic Issue 125.II.7 was evaluated to determine if the disadvantages of the automatic auxiliary feedwater system (AFW) isolation system, such as reduced AFW system reliability, outweighed the benefits provided by automatic AFW isolation to a steam generator during a steam or feed line break accident. Reactor plants with automatic AFW isolation systems from each pressurized water reactor (PWR) vendor were evaluated by determining the automatic isolation system's contribution to the core damage frequency (CDF) and determining any CDF increase or decrease that would occur if the system were removed. The CDF changes were used to estimate the change to the consequences or public risk due to removing the isolation system. Recent probabilistic risk assessments (PRAs) for a reactor plant from each PWR vendor were used to quantify the changes to CDFs and risks. The findings of this study indicate that the automatic AFW isolation system does not contribute significantly to the CDF or public risk for any of the plants evaluated. Removing the AFW isolation system resulted in a slight decrease in CDF and risk in some plants and caused a slight increase in CDF and risk in others
Additional details
Publishing Information
- Imprint Title
- Sixteenth water reactor safety information meeting. Volume 1: Plenary session, Decontamination and decommissioning, License renewal, Human factors, generic issues, Risk analysis/PRA applications, Innovative concepts for increased safety of advanced power reactors
- Imprint Pagination
- 561 p.
- Journal Page Range
- p. 265-278.
- Report number
- NUREG/CP--0097-Vol.1
Conference
- Title
- 16. water reactor safety information meeting.
- Dates
- 24-27 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22019080
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOMATION; AVAILABILITY; COST BENEFIT ANALYSIS; ERRORS; EVALUATION; FEEDWATER; LOSS OF COOLANT; PIPES; PROBABILITY; PWR TYPE REACTORS; RADIATION DOSES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR OPERATORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; RUPTURES; SENSITIVITY ANALYSIS; STEAM GENERATORS; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; COOLING SYSTEMS; ECONOMIC ANALYSIS; ENRICHED URANIUM REACTORS; FAILURES; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PERSONNEL; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8810155--Vol.1.