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At 2325 (CST) on 01/26/2016, Unit 1 was ma … At 2325 (CST) on 01/26/2016, Unit 1 was manually tripped due to loss of Feedwater on 'C' S/G (Steam Generator). The loss of Feedwater was a result of a failure on 'C' S/G Main Feedwater Regulating Valve that caused the valve to travel closed with no Operator action. Auxiliary Feedwater and Feedwater Isolation actuated as designed. All Control and Shutdown Rods fully inserted. Intermediate Range Nl 36 (Nuclear Instrument) failed above P10 and, as a result, Source Range Nuclear Instruments were manually energized. No primary or secondary relief valves opened. There were no electrical problems. Normal operating temperature and pressure (NOT/NOP) is 567 degrees F and 2235 psig. There were no significant TS LCOs entered.</br> </br>This event was not significant to the health and safety of the public based on all safety systems performed as designed.</br>Unit 2 was not affected.</br>Decay heat removal is being controlled via Steam Dumps. Offsite power is in the normal electrical lineup.</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
05:25:00, 27 January 2016 +
51,687 +
01:44:00, 27 January 2016 +
05:25:00, 27 January 2016 +
At 2325 (CST) on 01/26/2016, Unit 1 was ma … At 2325 (CST) on 01/26/2016, Unit 1 was manually tripped due to loss of Feedwater on 'C' S/G (Steam Generator). The loss of Feedwater was a result of a failure on 'C' S/G Main Feedwater Regulating Valve that caused the valve to travel closed with no Operator action. Auxiliary Feedwater and Feedwater Isolation actuated as designed. All Control and Shutdown Rods fully inserted. Intermediate Range Nl 36 (Nuclear Instrument) failed above P10 and, as a result, Source Range Nuclear Instruments were manually energized. No primary or secondary relief valves opened. There were no electrical problems. Normal operating temperature and pressure (NOT/NOP) is 567 degrees F and 2235 psig. There were no significant TS LCOs entered.</br> </br>This event was not significant to the health and safety of the public based on all safety systems performed as designed.</br>Unit 2 was not affected.</br>Decay heat removal is being controlled via Steam Dumps. Offsite power is in the normal electrical lineup.</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified. +
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Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
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05:25:00, 27 January 2016 +
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