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ENS 52295
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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
At 1338 CDT, a spurious electrical fault o … At 1338 CDT, a spurious electrical fault on a unit substation motor control center caused a spurious feedwater isolation and required a manual reactor trip on Unit 2 Byron Station due to lowering steam generator level. Auxiliary feedwater automatically actuated to supply feedwater flow and is maintaining steam generator level within procedurally required levels.</br>The motor control center fault resulted in feedwater isolations on two of four steam generators. All rods inserted during the trip. Decay heat is being removed via the steam dumps to condenser. Plant response to the trip was uncomplicated. Unit 2 is in a normal shutdown electrical lineup with power available from offsite. The grid is stable. Byron Station Unit 1 is at 95% power and stable and was unaffected by the transient on Unit 2. The cause of the motor control center fault is under investigation.</br>The licensee has notified the NRC Resident Inspector and will be issuing a press release concerning the manual reactor trip.elease concerning the manual reactor trip.  +
Discovered date
18:38:00, 12 October 2016  +
ENS id number
52,295  +
Emergency class
Non Emergency +
Entered date
15:17:00, 12 October 2016  +
Event date
18:38:00, 12 October 2016  +
Event description
At 1338 CDT, a spurious electrical fault o … At 1338 CDT, a spurious electrical fault on a unit substation motor control center caused a spurious feedwater isolation and required a manual reactor trip on Unit 2 Byron Station due to lowering steam generator level. Auxiliary feedwater automatically actuated to supply feedwater flow and is maintaining steam generator level within procedurally required levels.</br>The motor control center fault resulted in feedwater isolations on two of four steam generators. All rods inserted during the trip. Decay heat is being removed via the steam dumps to condenser. Plant response to the trip was uncomplicated. Unit 2 is in a normal shutdown electrical lineup with power available from offsite. The grid is stable. Byron Station Unit 1 is at 95% power and stable and was unaffected by the transient on Unit 2. The cause of the motor control center fault is under investigation.</br>The licensee has notified the NRC Resident Inspector and will be issuing a press release concerning the manual reactor trip.elease concerning the manual reactor trip.  +
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ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +, ENS 52295 +  and ENS 52295 +
Initial power
90  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 12 October 2016  +
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>.
01:44:02, 2 March 2018  +
NRC officer
Howie Crouch +
Notification date
15:17:00, 12 October 2016  +
Originated by
Jim Lynde +
Reactor critical
true  +
Reactor scram
true  +
Reactor type
Westinghouse PWR 4-Loop +
Region
NRC Region 3 +
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
-0.14 d (-3.35 hours, -0.0199 weeks, -0.00459 months)  +
Scram
Manual Scram +
Site
Byron +
Start date
18:38:00, 12 October 2016  +
State
Illinois +
System
Steam Generator +, Feedwater +  and Auxiliary Feedwater +
Title
Manual Reactor Trip Due to Spurious Feedwater Isolation  +
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http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2016/20161013en.html#en52295  +
Unit
2  +
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