Feedwater transient and small break loss of coolant accident analyses for the Bellefonte Nuclear Plant
Description
Specific sequences that may lead to core damage were analyzed for the Bellefonte nuclear plant as part of the US Nuclear Regulatory Commission's Severe Accident Sequence Analysis Program. The RELAP5, SCDAP, and SCDAP/RELAP5 computer codes were used in the analyses. The two main initiating events investigated were a loss of all feedwater to the steam generators and a small cold leg break loss of coolant accident. The transients of primary interest within these categories were the TMLB' and S2D sequences. Variations on systems availability were also investigated. Possible operator actions that could prevent or delay core damage were identified, and two were investigated for a small break transient. All of the transients were analyzed until either core damage began or long-term decay heat removal was established. The analyses showed that for the sequences considered the injection flow from one high-pressure injection pump was necessary and sufficient to prevent core damage in the absence of operator actions. Operator actions were able to prevent core damage in the S2D sequence; no operator actions were available to prevent core damage in the TMLB' sequence
Availability note (English)
Available from NTIS, PC A06/MF A01 - GPO as TI87007172.
Files
Additional details
Publishing Information
- Imprint Pagination
- 117 p.
- Report number
- NUREG/CR--4741
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19033083
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BELLEFONTE-1 REACTOR; BELLEFONTE-2 REACTOR; EXPERIMENTAL DATA; FAILURE MODE ANALYSIS; FUEL CANS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; QUENCHING; RISK ASSESSMENT; SCRAM; TRANSIENTS; VERY HIGH TEMPERATURE
- Descriptors DEC
- ACCIDENTS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2471.