The most recent core reload design verification physics testing done at Southern Nuclear Company’s (SNC) Vogtle Unit 2, performed prior to initial power operations in operating cycle 12, was successfully completed while the reactor was at least 1% ΔK/K subcritical. The testing program used was the first application of the Subcritical Physics Testing (SPT) program developed by the Westinghouse Electric Company LLC. The SPT program centers on the application of the Westinghouse Subcritical Rod Worth Measurement (SRWM) methodology that was developed in cooperation with the Vogtle Reactor Engineering staff. The SRWM methodology received U. S. Nuclear Regulatory Commission (NRC) approval in August of 2005. The first application of the SPT program occurred at Vogtle Unit 2 in October of 2005. The results of the core design verification measurements obtained during the SPT program demonstrated excellent agreement with prediction, demonstrating that the predicted core characteristics were in excellent agreement with the actual operating characteristics of the core. This paper presents an overview of the SPT Program used at Vogtle Unit 2 during operating cycle 12, and a discussion of the critical path outage time savings the SPT program is capable of providing.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
Plant Outage Time Savings Provided by Subcritical Physics Testing at Vogtle Unit 2
Philip Cupp,
Philip Cupp
Southern Nuclear Company Vogtle Station, Waynesboro, GA
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M. D. Heibel
M. D. Heibel
Westinghouse Electric Company, Pittsburgh, PA
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Philip Cupp
Southern Nuclear Company Vogtle Station, Waynesboro, GA
M. D. Heibel
Westinghouse Electric Company, Pittsburgh, PA
Paper No:
ICONE14-89177, pp. 91-95; 5 pages
Published Online:
September 17, 2008
Citation
Cupp, P, & Heibel, MD. "Plant Outage Time Savings Provided by Subcritical Physics Testing at Vogtle Unit 2." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 91-95. ASME. https://doi.org/10.1115/ICONE14-89177
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