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Category:Accident Sequence Precursor (ASP) Analysis
MONTHYEARML23074A0752023-03-16016 March 2023 Transmittal of Final Surry Power Station, Unit 1 Accident Sequence Precursor Report (EPID R-2016-ASP-0001) ML20168A7342020-06-16016 June 2020 Final ASP Analysis - Surry 1 (LER 280-73-005) ML20156A2592020-06-0404 June 2020 Final ASP Analysis - Surry 2 (LER 281-83-055) ML20156A2582020-06-0404 June 2020 Final ASP Analysis - Surry 2 (LER 281-83-005) ML20156A2572020-06-0404 June 2020 Final ASP Analysis - Surry 1 (LER 280-88-011) ML20156A2562020-06-0404 June 2020 Final ASP Analysis - Surry 1 (LER 280-84-011) ML20140A2112020-05-19019 May 2020 Final ASP Analysis - Surry 2 (LER 280-91-017) ML20135H2982020-05-14014 May 2020 Final ASP Analysis - Oconee 3 (LER 287-97-003) ML20114E2662020-05-12012 May 2020 Final ASP Analysis - Surry 1 and 2 (LER 280-01-001) 2023-03-16
[Table view] Category:Final
MONTHYEARML23074A0752023-03-16016 March 2023 Transmittal of Final Surry Power Station, Unit 1 Accident Sequence Precursor Report (EPID R-2016-ASP-0001) ML20168A7342020-06-16016 June 2020 Final ASP Analysis - Surry 1 (LER 280-73-005) ML20156A2592020-06-0404 June 2020 Final ASP Analysis - Surry 2 (LER 281-83-055) ML20156A2582020-06-0404 June 2020 Final ASP Analysis - Surry 2 (LER 281-83-005) ML20156A2572020-06-0404 June 2020 Final ASP Analysis - Surry 1 (LER 280-88-011) ML20156A2562020-06-0404 June 2020 Final ASP Analysis - Surry 1 (LER 280-84-011) ML20140A2112020-05-19019 May 2020 Final ASP Analysis - Surry 2 (LER 280-91-017) ML20135H2982020-05-14014 May 2020 Final ASP Analysis - Oconee 3 (LER 287-97-003) ML20114E2662020-05-12012 May 2020 Final ASP Analysis - Surry 1 and 2 (LER 280-01-001) 2023-03-16
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LER 281/83-005 Event
Description:
Trip with AFW Pump Inoperable Date of Event: February 11, 1983 Plant: Surry 2 Summary Surry Unit 2 was operating at full power on February 11, 1983 when the turbine-driven auxiliary feedwater (AFW) pump tripped during testing. The turbine governor was found to be defective, causing the turbine to trip on over-speed. Corrosion in the regulator piston in the pump governor valve prevented the piston from moving freely, which led to a pump over-speed trip.
Since a trip was reported on February 8, 1983, this event was modeled as a trip with the turbine-driven AFW pump assumed to be inoperable. The conditional core damage probability estimated for this event is 3.8x10-6. The dominant sequence involves a transient with reactor trip success, failure of main and auxiliary feed water, and failure of feed-and-bleed cooling.