ENS 45045: Difference between revisions

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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 To Feed Regulating Valve Failure
| 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

ENS 45045 +/-
Where
Sequoyah Tennessee Valley Authority icon.png
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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