Feed-and-bleed cooling analysis for Millstone Unit 2

Conference · Wed Nov 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6120268

Peeler, G B ^[1]; Dube, D A ^[2]; Ward, L W ^[3]

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1. Reactor Transient Analysis, Pennsville, NJ (USA)
2. Northeast Utilities Service Company, Hartford, CT (USA)
3. Idaho National Engineering Laboratory, Idaho Falls (USA)

The NULAP5 computer code, Northeast Utilities version of RELAP5, was used to perform best-estimate loss-of-coolant accident (LOCA) and non-LOCA transient analyses in support of the Millstone Unit 2 Probabilistic Safety Study. This paper summarizes the results of those analyses related to the feed-and-bleed operation (also called once-through cooling) following a complete loss of feedwater. Millstone Unit 2 is a 2 {times} 4 loop, 2,700-MW(thermal) Combustion Engineering designed pressurized water reactor. NULAP5 was used to define the equipment availability and operator response times that would yield acceptable cladding temperature response on a short-term basis and prevent sustained core uncovery on a long-term basis for feed-and-bleed scenarios. The overall trends of several analyses were also reproduced on the Millstone Unit 2 plant simulator when the transient conditions were within the predictive capabilities of the simulator.

• OSTI ID: 6120268
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

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