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[en] Steam generator cleaning procedure is discussed including description of Rinse phase, Heatup phase, Acid phase and the final Rinsing and Passivation phase. Results are summarized and it is concluded that preoperational chemical cleaning of the Sequoyah Nuclear Plant Unit 1 steam generators was an overall success, having accomplished the purposes of removing the rust and debris from the units as well as demonstrating the viability of the cleaning process. The reasons are presented why the fill-and-drain technique is believed to have considerable merit over a continuous circulation technique in steam generator applications

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[en] The investigation conducted at the Tennessee Valley Authority's Sequoyah Nuclear Power Plant to determine and correct increasing vibrations in the vertical reactor coolant pumps is described. Diagnostic procedures to determine the vibration causes and evaluate the corractive measures taken are also described

[en] The report describes work done on the Reactor Safety Study Methodology Applications Program. The accident sequences which dominate risk have been identified for the Sequoyah No. 1 pressurized water reactor (PWR) power plant. A comparison of the systems and accident sequences is made between the Sequoyah plant and the PWR plant used in the Reactor Safety Study

[en] The accident at Three Mile Island subjected loose parts monitoring system charge converters to moderate levels of radiation that caused them to fail. Two charge converters exhibiting similar failure symptoms were removed from an operating plant, Sequoyah Unit 1, and examined to determine their failure modes and to estimate the total radiation doses received by each. Radiation degradation of the circuit was found to be highly dependent on the value of a select resistor

[en] In April 1983 an ASME Performance Test was conducted on the Sequoyah 1 nuclear turbine-generator unit. Test data was collected using a mobile computer-controlled data-acquisition system. Excellent and consistent test results were achieved which showed that the unit performed better than expected. Earlier calorimetric analysis had indicated that the unit was not generating the expected electrical output. These earlier results were based on final feedwater flow measurement using permanently-installed station venturis. The ASME tests, which employed calibrated ASME throat-tap nozzles to measure feedwater flow, showed that the permanently-installed venturis had been indicating high, thereby causing the unit to be operated at less than 100% thermal power prior to the ASME test. The causes of this discrepancy are discussed in the paper. This paper includes a description of the test program and testing procedures and the performance of the major components of the heat cycle

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