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On March 1 7 , 2001, at approximately 2 1 … On March 1 7 , 2001, at approximately 2 1 1 3 , Beaver Valley Power Station Unit No. 2 received alarms for steam flow/ feedwater flow mismatch and 4160 volt motor overcurrent alarms. It was recognized that steam generator water levels were decreasing, a condensate pump had tripped, and a main feedwater pump had tripped. Implementing Abnormal Operating Procedure 2 . 24 . 1 , Loss of Feedwater, the Nuclear Shift Supervisor ordered a manual reactor trip.</br></br>However, while this action was being conducted, an automatic reactor trip properly initiated in response to a low-low steam generator water level in the "B" steam generator.</br></br>All control rods fully inserted into the reactor core and all required safety systems operated as designed. Emergency Operating Procedure E-0 for Reactor Trip was performed and the plant was stabilized in Mode 3. The automatic initiation of a reactor trip by the Reactor Protection System is reportable pursuant to 10 CFR 50.72 (b) (2) (iv) (B) and 10 CFR 50.73(a)(2) (iv) (A) .</br></br>The cause of the automatic trip was the tripping of the "A" Condensate Pump, 2CNM-P21A, due to electrical joint failure of its "C" phase power lead. This failure was attributed to a deficient joint configuration whereby a combination of long term heating, accelerated oxidation, and marginal sizing of the motor cable and terminal lugs resulted in an ultimate catastrophic failure of the joint. The safety significance for this event was small.ety significance for this event was small. +
March 17, 2001 +
On March 1 7 , 2001, at approximately 2 1 … On March 1 7 , 2001, at approximately 2 1 1 3 , Beaver Valley Power Station Unit No. 2 received alarms for steam flow/ feedwater flow mismatch and 4160 volt motor overcurrent alarms. It was recognized that steam generator water levels were decreasing, a condensate pump had tripped, and a main feedwater pump had tripped. Implementing Abnormal Operating Procedure 2 . 24 . 1 , Loss of Feedwater, the Nuclear Shift Supervisor ordered a manual reactor trip.</br></br>However, while this action was being conducted, an automatic reactor trip properly initiated in response to a low-low steam generator water level in the "B" steam generator.</br></br>All control rods fully inserted into the reactor core and all required safety systems operated as designed. Emergency Operating Procedure E-0 for Reactor Trip was performed and the plant was stabilized in Mode 3. The automatic initiation of a reactor trip by the Reactor Protection System is reportable pursuant to 10 CFR 50.72 (b) (2) (iv) (B) and 10 CFR 50.73(a)(2) (iv) (A) .</br></br>The cause of the automatic trip was the tripping of the "A" Condensate Pump, 2CNM-P21A, due to electrical joint failure of its "C" phase power lead. This failure was attributed to a deficient joint configuration whereby a combination of long term heating, accelerated oxidation, and marginal sizing of the motor cable and terminal lugs resulted in an ultimate catastrophic failure of the joint. The safety significance for this event was small.ety significance for this event was small. +
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04:46:03, 1 December 2017 +
May 9, 2001 +
March 17, 2001 +
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