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Auxiliary Feedwater actuation due to low s … Auxiliary Feedwater actuation due to low steam generator level following a manual reactor trip.</br>At 0702 on 10/15/05, a manual reactor trip was initiated due to decreasing level on the 3C steam generator. Auxiliary Feedwater system actuated as expected due to post-trip steam generator level decrease. 3C steam generator level was restored using Auxiliary and Main feed. The cause of the loss of steam generator level control is under investigation. </br>The plant is stable in Mode 3 with the Auxiliary Feedwater system in standby.</br>All control rods fully inserted. The decay heat removal path is normal feedwater through the steam generators and out the atmospheric relief valves. There are no primary to secondary steam generator tube leaks. Safety related electrical busses are powered via normal offsite power. Emergency diesel generators are available if needed. There was no impact on Unit 4.</br>The licensee notified the NRC Resident Inspector.</br> * * * UPDATE AT 1147 ON 10/19/05 FROM E. TREMBLAY TO P. SNYDER * * *</br>Updated to include notification under 10 CFR 50.72 (b)(2) for manual reactor trip.</br>The licensee notified the NRC Resident Inspector. R2DO (Ernstes) notified.sident Inspector. R2DO (Ernstes) notified. +
11:02:00, 15 October 2005 +
08:54:00, 15 October 2005 +
11:02:00, 15 October 2005 +
Auxiliary Feedwater actuation due to low s … Auxiliary Feedwater actuation due to low steam generator level following a manual reactor trip.</br>At 0702 on 10/15/05, a manual reactor trip was initiated due to decreasing level on the 3C steam generator. Auxiliary Feedwater system actuated as expected due to post-trip steam generator level decrease. 3C steam generator level was restored using Auxiliary and Main feed. The cause of the loss of steam generator level control is under investigation. </br>The plant is stable in Mode 3 with the Auxiliary Feedwater system in standby.</br>All control rods fully inserted. The decay heat removal path is normal feedwater through the steam generators and out the atmospheric relief valves. There are no primary to secondary steam generator tube leaks. Safety related electrical busses are powered via normal offsite power. Emergency diesel generators are available if needed. There was no impact on Unit 4.</br>The licensee notified the NRC Resident Inspector.</br> * * * UPDATE AT 1147 ON 10/19/05 FROM E. TREMBLAY TO P. SNYDER * * *</br>Updated to include notification under 10 CFR 50.72 (b)(2) for manual reactor trip.</br>The licensee notified the NRC Resident Inspector. R2DO (Ernstes) notified.sident Inspector. R2DO (Ernstes) notified. +
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08:54:00, 15 October 2005 +
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11:02:00, 15 October 2005 +
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