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On 07/13/2009 at 00:38 EDT a planned manua … On 07/13/2009 at 00:38 EDT a planned manual reactor trip was initiated on Unit 2 based on increased, unidentified RCS leakage. The RCS leakage had increased over a four day period. The downpower was initiated at 21:32 EDT from 100% power and proceeded in a controlled manner to 25% power. The reactor was manually tripped at 00:38 EDT, as planned. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed and the unit was stabilized in Mode 3. Decay heat was removed by the Steam Bypass Control System (SBCS) to the condenser. The Main Feedwater Pump unexpectedly tripped on low suction pressure just prior to the reactor trip, but was recovered prior to levels reaching the Auxiliary Feedwater Actuation (AFAS) setpoint. There were no further major equipment failures identified post trip. </br>On 7/13/2009 at 07:00 EDT a Containment walkdown confirmed the leak was caused by a J-joint weld defect on the 2B2 RCP Seal injection line. The leak is classified as reactor coolant pressure boundary leakage.</br>The plant is in the process of cooling down to enter Mode 5 as required by Technical Specification 3.4.6.2.a.</br>This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(A). Additional investigation is being performed to determine the cause of the leak.</br>The initial leak rate was less than 0.2 gpm. The repair will require taking the plant to a reduced inventory.</br>The licensee notified the NRC Resident Inspectorcensee notified the NRC Resident Inspector +
11:00:00, 13 July 2009 +
45,200 +
11:37:00, 13 July 2009 +
11:00:00, 13 July 2009 +
On 07/13/2009 at 00:38 EDT a planned manua … On 07/13/2009 at 00:38 EDT a planned manual reactor trip was initiated on Unit 2 based on increased, unidentified RCS leakage. The RCS leakage had increased over a four day period. The downpower was initiated at 21:32 EDT from 100% power and proceeded in a controlled manner to 25% power. The reactor was manually tripped at 00:38 EDT, as planned. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed and the unit was stabilized in Mode 3. Decay heat was removed by the Steam Bypass Control System (SBCS) to the condenser. The Main Feedwater Pump unexpectedly tripped on low suction pressure just prior to the reactor trip, but was recovered prior to levels reaching the Auxiliary Feedwater Actuation (AFAS) setpoint. There were no further major equipment failures identified post trip. </br>On 7/13/2009 at 07:00 EDT a Containment walkdown confirmed the leak was caused by a J-joint weld defect on the 2B2 RCP Seal injection line. The leak is classified as reactor coolant pressure boundary leakage.</br>The plant is in the process of cooling down to enter Mode 5 as required by Technical Specification 3.4.6.2.a.</br>This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(A). Additional investigation is being performed to determine the cause of the leak.</br>The initial leak rate was less than 0.2 gpm. The repair will require taking the plant to a reduced inventory.</br>The licensee notified the NRC Resident Inspectorcensee notified the NRC Resident Inspector +
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00:00:00, 13 July 2009 +
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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