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On 11/3/08 at 2322, Unit 2 was manually trOn 11/3/08 at 2322, Unit 2 was manually tripped due to the failure of Loop 4 Feed Water Reg. Valve (FRV Controller). Manual control was attempted to control level in Loop 4 Steam Generator (S/G); however, Loop 4 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</br>The Loop 4 FRV did isolate from the Feedwater isolation signal.</br>The Plant is being maintained in Mode 3 at NOT/NOP, 547 F and 2235 psig, with AFW supplying the S/G's and Steam Dumps removing decay heat.</br>Additionally, Unit 2 has an indication of a primary leak inside lower containment. The leak rate is calculated to be approximately 2.0 gallons per minute. Based on current indications, the leak is suspected to be from a Pressurizer level transmitter</br>No primary system or steam generator safety valves opened due to this trip. An investigation has been initiated to determine the cause of the Loop 4 Feed Water Reg. Valve (FRV Controller) failure and the source of the approximately 2.0 gallons per minute primary leak. A recovery plan will be developed.</br>Pressurizer (PRZ) level is stable. All safety related systems are available and OPERABLE for safe plant shutdown. There is no impact on Unit 1. The loop 2 S/G blowdown sample line valve did not go closed as expected on the Feedwater isolation signal. The licensee is taking action to isolate it. </br> </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM LARRY PRUETT TO JOE O'HARA AT 0001 ON 11/5/08 * * *</br>The Sequoyah Nuclear Plant Unit - 2 reactor coolant system unidentified leakage was terminated on Nov. 4, 2008 @ 2205 hours when a manual valve was closed isolating the reactor coolant system from the leak location." </br>The licensee closed the root valve to the PZR pressure channel 2-VLV-68-446A.</br>The licensee will notify the NRC Resident Inspector.</br>Notified R2DO(Desai)C Resident Inspector. Notified R2DO(Desai)  +
04:22:00, 4 November 2008  +
44,627  +
02:58:00, 4 November 2008  +
04:22:00, 4 November 2008  +
On 11/3/08 at 2322, Unit 2 was manually trOn 11/3/08 at 2322, Unit 2 was manually tripped due to the failure of Loop 4 Feed Water Reg. Valve (FRV Controller). Manual control was attempted to control level in Loop 4 Steam Generator (S/G); however, Loop 4 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</br>The Loop 4 FRV did isolate from the Feedwater isolation signal.</br>The Plant is being maintained in Mode 3 at NOT/NOP, 547 F and 2235 psig, with AFW supplying the S/G's and Steam Dumps removing decay heat.</br>Additionally, Unit 2 has an indication of a primary leak inside lower containment. The leak rate is calculated to be approximately 2.0 gallons per minute. Based on current indications, the leak is suspected to be from a Pressurizer level transmitter</br>No primary system or steam generator safety valves opened due to this trip. An investigation has been initiated to determine the cause of the Loop 4 Feed Water Reg. Valve (FRV Controller) failure and the source of the approximately 2.0 gallons per minute primary leak. A recovery plan will be developed.</br>Pressurizer (PRZ) level is stable. All safety related systems are available and OPERABLE for safe plant shutdown. There is no impact on Unit 1. The loop 2 S/G blowdown sample line valve did not go closed as expected on the Feedwater isolation signal. The licensee is taking action to isolate it. </br> </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM LARRY PRUETT TO JOE O'HARA AT 0001 ON 11/5/08 * * *</br>The Sequoyah Nuclear Plant Unit - 2 reactor coolant system unidentified leakage was terminated on Nov. 4, 2008 @ 2205 hours when a manual valve was closed isolating the reactor coolant system from the leak location." </br>The licensee closed the root valve to the PZR pressure channel 2-VLV-68-446A.</br>The licensee will notify the NRC Resident Inspector.</br>Notified R2DO(Desai)C Resident Inspector. Notified R2DO(Desai)  +
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0.0255 d (0.613 hours, 0.00365 weeks, 8.390025e-4 months)  +
00:00:00, 5 November 2008  +
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02:13:16, 2 March 2018  +
02:58:00, 4 November 2008  +
-0.0583 d (-1.4 hours, -0.00833 weeks, -0.00192 months)  +
04:22:00, 4 November 2008  +
Manual Reactor Trip Due to Feedwater Reg Valve Failure  +
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2  +