Accident Management Actions in an Upper-Head Small-Break Loss-of-Coolant Accident with High-Pressure Safety Injection Failed

Author:

Queral César1,González-Cadelo Juan1,Jimenez Gonzalo1,Villalba Ernesto1

Affiliation:

1. Universidad Politécnica de Madrid, C/Alenza 4, 28003 Madrid, Spain

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference44 articles.

1. “Davis-Besse Reactor Pressure Vessel Head Degradation. Overview, Lessons Learned, and NRC Actions Based on Lessons Learned,” NUREG/BR-0353, Rev. 1, U.S. Nuclear Regulatory Commission (Aug. 2008).

2. “Root Cause Analysis Report—Significant Degradation of the Reactor Pressure Vessel Head,” CR 2002-0891 (Apr. 15, 2002) and CR 2002-0891, Rev.1 (Aug. 27, 2002), First Energy Nuclear Operating Company, Davis Besse Nuclear Power Station.

3. “Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations,” NRC Generic Letter 97-01, U.S. Nuclear Regulatory Commission.

4. “Inadequate Core Cooling Studies of Scenarios with Feedwater Available,” WCAP-9754, Westinghouse Electric Corporation (1980) (nonproprietary version).

5. “Analysis of Delayed Coolant Pump Trip During Small Loss of Coolant Accidents for Westinghouse Nuclear Steam Supply Systems,” WCAP-9585, Westinghouse Electric Corporation (1979) (nonproprietary version).

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