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On 07/09/10 at 0647 (CDT) hours, control r … On 07/09/10 at 0647 (CDT) hours, control room personnel initiated a manual reactor trip of Unit 2 from approximately 64% power as a result of a failure of the "A" feedwater regulating valve (FRV). All (other) systems functioned as expected. All rods fully inserted into the core. The unit is stable in MODE 3 at normal RCS (Reactor Coolant System) pressure and temperature. The cause of the FRV failure is being investigated.</br>This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).</br>The unit electrical power is lined up to offsite power in a normal configuration. Decay heat is being removed from the steam generator through the steam dumps to the main condenser. The FRV failed open and the valve controller was unable to place the FRV into the correct position. The steam generator HI-Hi level provided a feedwater isolation signal and a high level lockout of the FRV. Currently, the feedwater bypass valve is controlling steam generator level. There was no impact on Unit 1.</br>The licensee has notified the NRC Resident Inspector.e has notified the NRC Resident Inspector. +
11:47:00, 9 July 2010 +
46,080 +
10:44:00, 9 July 2010 +
11:47:00, 9 July 2010 +
On 07/09/10 at 0647 (CDT) hours, control r … On 07/09/10 at 0647 (CDT) hours, control room personnel initiated a manual reactor trip of Unit 2 from approximately 64% power as a result of a failure of the "A" feedwater regulating valve (FRV). All (other) systems functioned as expected. All rods fully inserted into the core. The unit is stable in MODE 3 at normal RCS (Reactor Coolant System) pressure and temperature. The cause of the FRV failure is being investigated.</br>This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).</br>The unit electrical power is lined up to offsite power in a normal configuration. Decay heat is being removed from the steam generator through the steam dumps to the main condenser. The FRV failed open and the valve controller was unable to place the FRV into the correct position. The steam generator HI-Hi level provided a feedwater isolation signal and a high level lockout of the FRV. Currently, the feedwater bypass valve is controlling steam generator level. There was no impact on Unit 1.</br>The licensee has notified the NRC Resident Inspector.e has notified the NRC Resident Inspector. +
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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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