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An automatic reactor scram occurred due to … An automatic reactor scram occurred due to lowering reactor water level. Digital feedwater tuning activities were in progress at the time of the scram. All systems functioned as designed. The reactor water level has been restored to normal level band. The plant is stable in Hot Shutdown. There were no ECCS injections.</br>At the time of the scram, the feedwater pump was in manual control for feedwater tuning. When water level started going down quickly, the operator was not able to restore sufficient feedwater flow before the level 3 (water level low) actuation. All control rods fully inserted on the scram. No valves repositioned and no safety or relief valves lifted after the scram. Reactor water level is being maintained with the motor feed pump and decay heat is being removed to the main condenser. The plant is in the normal shutdown electrical lineup. Reactor pressure is 509 psi and stable.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM FREDERICK SMITH TO FANGIE JONES ON 05/17/07 AT 1301 * * *</br>This call is to clarify information provided in notification Event Number 43363 made by the Perry Nuclear Power Plant on May 15, 2007. The second paragraph, fourth sentence of the notification states: 'No valves repositioned and no safety or relief valves lifted after the scram.' The intent of the portion of the sentence 'No valves repositioned' was supposed to be in reference to the reporting requirement in 10 CFR 50.72(b)(3)(iv) to report any event or condition that results in valid actuation of general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).</br> </br>The event on May 15, 2007, did not meet the 'containment isolation valves in more than one system / MSIVs criterion', however, subsequent review of the event identified that Residual Heat Removal 'B' Heat Exchanger Second Vent to Suppression Pool Containment Isolation Valve 1E12-F073B, closed, as designed, in response to the reactor coolant level 3 (water level low) condition that was present during the event. No additional reporting criteria have been identified and this update has been provided to clarify the earlier statement.</br>The NRC Resident Inspector has been notified." </br>Notified R3 RDO, (Ring), and NRR EO, (Ross Lee).ed R3 RDO, (Ring), and NRR EO, (Ross Lee).
04:58:00, 15 May 2007 +
01:53:00, 15 May 2007 +
04:58:00, 15 May 2007 +
An automatic reactor scram occurred due to … An automatic reactor scram occurred due to lowering reactor water level. Digital feedwater tuning activities were in progress at the time of the scram. All systems functioned as designed. The reactor water level has been restored to normal level band. The plant is stable in Hot Shutdown. There were no ECCS injections.</br>At the time of the scram, the feedwater pump was in manual control for feedwater tuning. When water level started going down quickly, the operator was not able to restore sufficient feedwater flow before the level 3 (water level low) actuation. All control rods fully inserted on the scram. No valves repositioned and no safety or relief valves lifted after the scram. Reactor water level is being maintained with the motor feed pump and decay heat is being removed to the main condenser. The plant is in the normal shutdown electrical lineup. Reactor pressure is 509 psi and stable.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE FROM FREDERICK SMITH TO FANGIE JONES ON 05/17/07 AT 1301 * * *</br>This call is to clarify information provided in notification Event Number 43363 made by the Perry Nuclear Power Plant on May 15, 2007. The second paragraph, fourth sentence of the notification states: 'No valves repositioned and no safety or relief valves lifted after the scram.' The intent of the portion of the sentence 'No valves repositioned' was supposed to be in reference to the reporting requirement in 10 CFR 50.72(b)(3)(iv) to report any event or condition that results in valid actuation of general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs).</br> </br>The event on May 15, 2007, did not meet the 'containment isolation valves in more than one system / MSIVs criterion', however, subsequent review of the event identified that Residual Heat Removal 'B' Heat Exchanger Second Vent to Suppression Pool Containment Isolation Valve 1E12-F073B, closed, as designed, in response to the reactor coolant level 3 (water level low) condition that was present during the event. No additional reporting criteria have been identified and this update has been provided to clarify the earlier statement.</br>The NRC Resident Inspector has been notified." </br>Notified R3 RDO, (Ring), and NRR EO, (Ross Lee).ed R3 RDO, (Ring), and NRR EO, (Ross Lee).
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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>.
22:36:47, 24 September 2017 +
01:53:00, 15 May 2007 +
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04:58:00, 15 May 2007 +
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