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ENS 50551
Show incoming properties
Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge +  and 10 CFR 50.72#b3ivA +
Current power
0  +
Current reactor mode
Hot Shutdown +
Description
The Perry Power Plant experienced a reacto … The Perry Power Plant experienced a reactor scram during a shift of non-essential vital power supply to the alternate source. Feedwater was lost resulting in receiving a valid level 3 and level 2 signal. High Pressure Core Spray and Reactor Core Isolation Cooling started and injected. Reactor level and pressure have been stabilized to required bands. The motor feed pump has been started and is controlling level. High Pressure Core Spray and Reactor Core Isolation Cooling have been returned to standby.</br>During the scram, all rods fully inserted into the core. Decay heat is being removed via the steam dumps to the condenser. The electrical grid is stable and supplying plant loads. An emergency diesel generator started, as designed, as a result of the level 2 signal but did not load. No safety valves lifted as a result of the transient. The cause of the loss of feedwater is under investigation.</br>The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.</br>* * * UPDATE FROM DOUG SHORTER TO HOWIE CROUCH AT 0933 EDT ON 10/20/14 * * *</br>The plant is currently in Mode 3, stable with cooldown and depressurization to Mode 4 in progress. Level control is being provided by the motor feedwater pump. Troubleshooting of the cause of the scram and loss of feed water is on-going. </br>The initial notification identified 10CFR50.72(b)(3)(iv)(A), 'Specified System Actuation', as a reporting criteria. The specific system that actuated was not provided. As a result of receiving a reactor vessel water level 2 signal a containment/BOP isolation signal was received. All systems isolated as required and the plant is restoring isolated systems in accordance with procedure.</br>The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.</br>Notified R3DO (Pelke).Resident Inspector. Notified R3DO (Pelke).  +
Discovered date
06:18:00, 20 October 2014  +
ENS id number
50,551  +
Emergency class
Non Emergency +
Entered date
03:55:00, 20 October 2014  +
Event date
06:18:00, 20 October 2014  +
Event description
The Perry Power Plant experienced a reacto … The Perry Power Plant experienced a reactor scram during a shift of non-essential vital power supply to the alternate source. Feedwater was lost resulting in receiving a valid level 3 and level 2 signal. High Pressure Core Spray and Reactor Core Isolation Cooling started and injected. Reactor level and pressure have been stabilized to required bands. The motor feed pump has been started and is controlling level. High Pressure Core Spray and Reactor Core Isolation Cooling have been returned to standby.</br>During the scram, all rods fully inserted into the core. Decay heat is being removed via the steam dumps to the condenser. The electrical grid is stable and supplying plant loads. An emergency diesel generator started, as designed, as a result of the level 2 signal but did not load. No safety valves lifted as a result of the transient. The cause of the loss of feedwater is under investigation.</br>The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.</br>* * * UPDATE FROM DOUG SHORTER TO HOWIE CROUCH AT 0933 EDT ON 10/20/14 * * *</br>The plant is currently in Mode 3, stable with cooldown and depressurization to Mode 4 in progress. Level control is being provided by the motor feedwater pump. Troubleshooting of the cause of the scram and loss of feed water is on-going. </br>The initial notification identified 10CFR50.72(b)(3)(iv)(A), 'Specified System Actuation', as a reporting criteria. The specific system that actuated was not provided. As a result of receiving a reactor vessel water level 2 signal a containment/BOP isolation signal was received. All systems isolated as required and the plant is restoring isolated systems in accordance with procedure.</br>The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.</br>Notified R3DO (Pelke).Resident Inspector. Notified R3DO (Pelke).  +
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ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +, ENS 50551 +  and ENS 50551 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 20 October 2014  +
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>.
01:49:23, 2 March 2018  +
NRC officer
Howie Crouch +
Notification date
03:55:00, 20 October 2014  +
Originated by
Dan Kunzman +
Person
Howie Crouch +
Reactor critical
true  +
Reactor type
GE-6 +
Region
NRC Region 3 +
Reporting criterion
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +  and 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge +
Reporting time
-0.0992 d (-2.38 hours, -0.0142 weeks, -0.00326 months)  +
Scram
Automatic Scram +
Site
Perry +
Start date
06:18:00, 20 October 2014  +
State
Ohio +
System
Feedwater +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +  and High Pressure Core Spray +
Title
Automatic Reactor Scram on Loss of Feedwater  +
Topic
Reactor Vessel Water Level +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2014/20141021en.html#en50551  +
Unit
1  +
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