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ENS 51036
Show incoming properties
Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +  and 10 CFR 50.72(b)(3)(iv)(A), System Actuation +
Current power
0  +
Current reactor mode
Hot Standby +
Description
On 5/3/2015 during power ascension followi … On 5/3/2015 during power ascension following Refueling Outage 20, Steam Generator 'C' water level increased rapidly, causing a Feedwater isolation on high Steam Generator water level and an associated Turbine trip. The reactor was subsequently manually tripped.</br>At the start of the event, reactor power was approximately 22%. Plant staff was in the process of transferring from Main Feedwater Bypass Feed Regulating Valve control, used for low power control, to Main Feedwater Regulating Valve control as part of power ascension. When the Main Feedwater Regulating Valve for 'C' Steam Generator (AEFCV-530) was opened, it went to about 80% open, causing an overfeed of the 'C' Steam Generator. High Steam Generator water level in 'C' Steam Generator initiated an automatic Feedwater Isolation Signal, automatic Turbine Trip and automatic trip of the operating main feed pump. The operating crew initiated a manual reactor trip.</br>The Auxiliary Feedwater System automatically initiated as part of the plant response to the feedwater system transient.</br>The plant is presently stable in Mode 3. All equipment functioned normally, except the 'C' Main Feedwater Regulating Valve (AEFCV0530) which did not function to properly control Steam Generator level. This valve did function as designed to close on the Feedwater Isolation Signal.</br>NRC Resident Inspector has been contacted.NRC Resident Inspector has been contacted.  +
Discovered date
15:22:00, 3 May 2015  +
ENS id number
51,036  +
Emergency class
Non Emergency +
Entered date
12:56:00, 3 May 2015  +
Equipment trip
Turbine Trip +  and Reactor Trip +
Event date
15:22:00, 3 May 2015  +
Event description
On 5/3/2015 during power ascension followi … On 5/3/2015 during power ascension following Refueling Outage 20, Steam Generator 'C' water level increased rapidly, causing a Feedwater isolation on high Steam Generator water level and an associated Turbine trip. The reactor was subsequently manually tripped.</br>At the start of the event, reactor power was approximately 22%. Plant staff was in the process of transferring from Main Feedwater Bypass Feed Regulating Valve control, used for low power control, to Main Feedwater Regulating Valve control as part of power ascension. When the Main Feedwater Regulating Valve for 'C' Steam Generator (AEFCV-530) was opened, it went to about 80% open, causing an overfeed of the 'C' Steam Generator. High Steam Generator water level in 'C' Steam Generator initiated an automatic Feedwater Isolation Signal, automatic Turbine Trip and automatic trip of the operating main feed pump. The operating crew initiated a manual reactor trip.</br>The Auxiliary Feedwater System automatically initiated as part of the plant response to the feedwater system transient.</br>The plant is presently stable in Mode 3. All equipment functioned normally, except the 'C' Main Feedwater Regulating Valve (AEFCV0530) which did not function to properly control Steam Generator level. This valve did function as designed to close on the Feedwater Isolation Signal.</br>NRC Resident Inspector has been contacted.NRC Resident Inspector has been contacted.  +
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ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +, ENS 51036 +  and ENS 51036 +
Initial power
22  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 3 May 2015  +
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>.
01:47:52, 2 March 2018  +
NRC officer
Daniel Mills +
Notification date
12:56:00, 3 May 2015  +
Originated by
Larry Hauth +
Reactor critical
true  +
Reactor scram
true  +
Reactor type
Westinghouse PWR 4-Loop +
Region
NRC Region 4 +
Reporting criterion
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +  and 10 CFR 50.72(b)(3)(iv)(A), System Actuation +
Reporting time
-0.101 d (-2.43 hours, -0.0145 weeks, -0.00333 months)  +
Scram
Manual Scram +  and Automatic Scram +
Site
Wolf Creek +
Start date
15:22:00, 3 May 2015  +
State
Kansas +
System
Steam Generator +, Feedwater +  and Auxiliary Feedwater +
Title
Feedwater Isolation, Turbine Trip and Manual Reactor Trip During Power Ascension  +
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/2015/20150504en.html#en51036  +
Unit
1  +
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