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Category:Accident Sequence Precursor (ASP) Analysis
MONTHYEARML20168A5622020-06-16016 June 2020 Final ASP Analysis - Indian Point 3 (LER 286-77-003) ML20168A5602020-06-16016 June 2020 Final ASP Analysis - Indian Point 1 (LER 003-70-LTR) ML20149K3892020-05-28028 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-88-002).pdf ML20149K3882020-05-28028 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-84-015) ML20149K3872020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-88-020) ML20149K3862020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-86-035) ML20149K3852020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-86-017) ML20149K3842020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-85-016) ML20149K3832020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-83-005) ML20149K3822020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-82-019) ML20149K3812020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-80-006) ML20135G9652020-05-14014 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-91-001) ML20135G9662020-05-14014 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-92-007) ML20135G9672020-05-14014 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-90-005) ML20135G9682020-05-14014 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-92-011) IR 05000247/20020102020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (IR 050002472002010) ML20112J4042020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-99-015) ML20112J2392020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-00-001-01) 2020-06-16
[Table view] Category:Final
MONTHYEARML20168A5622020-06-16016 June 2020 Final ASP Analysis - Indian Point 3 (LER 286-77-003) ML20168A5602020-06-16016 June 2020 Final ASP Analysis - Indian Point 1 (LER 003-70-LTR) ML20149K3892020-05-28028 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-88-002).pdf ML20149K3882020-05-28028 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-84-015) ML20149K3872020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-88-020) ML20149K3862020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-86-035) ML20149K3852020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-86-017) ML20149K3842020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-85-016) ML20149K3832020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-83-005) ML20149K3822020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-82-019) ML20149K3812020-05-28028 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-80-006) ML20135G9652020-05-14014 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-91-001) ML20135G9662020-05-14014 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-92-007) ML20135G9672020-05-14014 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-90-005) ML20135G9682020-05-14014 May 2020 Final ASP Analysis - Indian Point 3 (LER 286-92-011) IR 05000247/20020102020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (IR 050002472002010) ML20112J4042020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-99-015) ML20112J2392020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (LER 247-00-001-01) 2020-06-16
[Table view] |
Text
LER 247/83-005 Event
Description:
Transient with the Turbine-Driven AFW Pump Inoperable Date of Event: March 8, 1983 Plant: Indian Point 2 Summary During normal operation on March 8, 1983, while the 22 turbine-driven auxiliary feedwater (AFW) pump was being brought up to operating speed for a bimonthly surveillance test, the outboard bearing began smoking and the pump was removed from service for maintenance. Inspection of the pump indicated that repacking was required. A trip had occurred less than a month prior to this event on February 13 (Licensed Operating Reactors, Status Summary Report (NUREG-0020),
published monthly, U.S. Nuclear Regulatory Commission, hereafter referred to as NUREG-0020).
Assuming that a bimonthly test indicates that a test was performed every two months, half the surveillance period of the turbine-driven AFW pump is a month.
Since the trip occurred less than a month earlier, it was assumed that the problem with the AFW
- pump existed at the time of the trip. This event was modeled as a transient with the turbine-driven train of AFW failed. The model for the failure of AFW given an anticipated transient without scram (ATWS) requires the use of 2 of 3 pumps. The AFW/ATWS probability was set to 0.04 to reflect the probability of failure for motor-driven pump 22 or motor-driven pump 23. The conditional core damage probability of this event is 3.9x10-6. The dominant core damage sequence involves a successful reactor trip, the failure of AFW, the failure of main feed water, and failure of feed and bleed.