ENS 45045: Difference between revisions
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StriderTol (talk | contribs) (Created page by program invented by Mark Hawes) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
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| event date = 05/06/2009 22:56 EDT | | event date = 05/06/2009 22:56 EDT | ||
| last update date = 05/07/2009 | | last update date = 05/07/2009 | ||
| title = Manual Reactor Trip Due | | title = Manual Reactor Trip Due to Feed Regulating Valve Failure | ||
| event text = On 5/6/09 at 2256 Sequoyah Unit-1 was manually tripped from 100% reactor power. The manual trip was in response to the failure of Loop 1 Feed Water Regulating Valve (FRV). Manual control was attempted to control level in Loop 1 Steam Generator however Loop 1 FRV failed to respond. A manual reactor trip was initiated as a result of this failure. In addition, Auxiliary Feedwater (AFW) initiated as required due to a Feedwater Isolation signal. The Loop 1 FRV did not isolate from the Feedwater Isolation signal, however the Loop 1 Feedwater Isolation Valve closed as designed. | | event text = On 5/6/09 at 2256 Sequoyah Unit-1 was manually tripped from 100% reactor power. The manual trip was in response to the failure of Loop 1 Feed Water Regulating Valve (FRV). Manual control was attempted to control level in Loop 1 Steam Generator however Loop 1 FRV failed to respond. A manual reactor trip was initiated as a result of this failure. In addition, Auxiliary Feedwater (AFW) initiated as required due to a Feedwater Isolation signal. The Loop 1 FRV did not isolate from the Feedwater Isolation signal, however the Loop 1 Feedwater Isolation Valve closed as designed. | ||
The Plant is currently being maintained in Mode 3 at NOT/NOP, approximately 547 [degrees] F and 2235 psig, with Auxiliary Feedwater supplying the steam generators and Steam Dumps to Main Condenser removing decay heat. | The Plant is currently being maintained in Mode 3 at NOT/NOP, approximately 547 [degrees] F and 2235 psig, with Auxiliary Feedwater supplying the steam generators and Steam Dumps to Main Condenser removing decay heat. |
Latest revision as of 22:12, 1 March 2018
Where | |
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Sequoyah Tennessee (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-2.45 h-0.102 days <br />-0.0146 weeks <br />-0.00336 months <br />) | |
Opened: | Pat Leahy 00:29 May 7, 2009 |
NRC Officer: | Howie Crouch |
Last Updated: | May 7, 2009 |
45045 - NRC Website
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