Semantic search
Site | Start date | Title | Description | |
---|---|---|---|---|
BYRON 2020-0085, 10 CFR 50.59 Summary Report | Byron | 10 December 2020 | 10 CFR 50.59 Summary Report | |
ML20339A040 | Ginna | 20 November 2020 | 9 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System, Sections 10.1 Thru 10.7 | |
ML20156A250 | Saint Lucie | 4 June 2020 | Final ASP Analysis - St. Lucie 2 (LER 389-84-011) | |
ML20135G955 | Fort Calhoun | 14 May 2020 | Final ASP Analysis - Fort Calhoun (LER 285-92-023) | |
ML19150A481 | Ginna | 10 May 2019 | Revision 28 to Updated Final Safety Analysis Report, Chapter 10, Sections 10.1 Thru 10.7 | |
05000286/LER-2017-004 | Indian Point | 3 November 2017 20 December 2017 | Reactor Trip Due to Main Generator Loss of Field LER 17-004-00 for Indian Point Unit 3, Regarding Reactor Trip Due to Main Generator Loss of Field | On November 3, 2017, at 2022 hours, with reactor power at 100 percent, Indian Point Unit 3 experienced an automatic reactor trip on a turbine trip, which was in response to a main generator trip. The main generator trip was initiated by actuation of the Generator Protection System due to a main generator loss of field. All control rods fully inserted and all required safety systems functioned properly. The plant was stabilized in hot standby with decay heat being removed by the main condenser. The Auxiliary Feedwater System (AFWS) automatically started as expected on steam generator low level to provide feedwater flow to the steam generators. The plant was stabilized in hot standby with decay heat being removed by the main condenser. The direct cause of the loss of main generator field was a failed Thyristor Firing Module drawer which affected proper operation of the redundant Thyristor Firing Module drawer. The root cause was determined to be that the Automatic Voltage Regulator (AVR) Firing Module power supplies have a latent design vulnerability where shared common output nodes are not isolated after a failure. A plant modification is proposed that will eliminate the condition by electrically isolating the AVR Firing Module power supplies upon failure. This event had no effect on the public health and safety. The event was reported to the Nuclear Regulatory Commission (NRC) on November 3, 2017 under 10 CFR 50.72(b)(2)(iv)(B) and 50.72(b)(3)(iv)(A) as an event that resulted in the automatic actuation of the Reactor Protection System when the reactor is critical and a valid actuation of the AFWS. |
ML18043B041 | Byron | 14 December 2017 | 2017 Byron Station Initial License Examination Administered Written Examination | |
ML18043A104 | Byron | 14 December 2017 | 2017 Byron Station Initial License Examination Proposed Written Examination | |
ML17076A216 | Callaway | 17 March 2017 | Final Safety Analysis Report, Revision OL-22, Chapter 10, Steam and Power Conversion System | |
ML16256A435 | Waterford | 25 August 2016 | Revision 309 to Final Safety Analysis Report, Chapter 8, Electric Power, Section 8.2 |