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ENS 52623
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)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +, 10 CFR 50.72#b3ivA +  and 10 CFR 50.72#b3vD +
Current power
0  +
Current reactor mode
Hot Standby +
Description
On 3/18/17 at 1107 (EDT), the Unit 3 react … On 3/18/17 at 1107 (EDT), the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. All three reactor coolant pumps (RCP) tripped and the 3B RCP was restarted for forced recirculation. The reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. In addition, Technical Specification 3.8.1.1, Action C requires a four hour report for the concurrent inoperability of the Unit 4 startup transformer to Unit 3 via the 3A 4kV bus and the Unit 3 3A diesel generator.</br>The NRC Senior Resident Inspector will be notified.</br>* * * UPDATE ON 3/18/2017 AT 1854 EDT FROM JAMES SPICHER TO BETHANY CECERE * * *</br>Update to previous report (EN 52623) to include additional reporting criteria.</br>On 3/18/17 at 1107 (EDT) the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. The 3A Emergency Diesel Generator (EDG) started on the loss of power signal but did not load, as designed, due to the bus fault. The 3A EDG was manually stopped at 1332. The Auxiliary Feedwater (AFW) System also initiated as expected. AFW was stopped at 1135. The actuations of the 3A EDG and AFW are reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A).</br>A loss of safety function affecting Units 3 and 4 occurred due to the loss of the 3A high head safety injection (HHSI) pump because it could not be powered from the faulted 3A 4kV bus with both Unit 4 HHSI pumps earlier (0624) removed from service due to planned maintenance. This caused three of the four HHSI pumps to be inoperable. The four HHSI pumps are shared by both Units 3 and 4. The safety function is achieved by two of the four HHSI pumps. Both Unit 4 HHSI pumps were restored to operable status at 1336. The loss of safety function is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D).</br>The Unit 3 reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. Unit 4 remains operating at 100% power.</br>The licensee will notify the NRC Resident Inspector.</br>Notified R2DO (Ehrhardt) and NRR EO (Miller).ified R2DO (Ehrhardt) and NRR EO (Miller).  
Discovered date
15:07:00, 18 March 2017  +
ENS
ENS 52623 +
ENS id number
52,623  +
Emergency class
Non Emergency +
Entered date
15:07:00, 18 March 2017  +
Equipment trip
Reactor Trip +
Event date
15:07:00, 18 March 2017  +
Event description
On 3/18/17 at 1107 (EDT), the Unit 3 react … On 3/18/17 at 1107 (EDT), the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. All three reactor coolant pumps (RCP) tripped and the 3B RCP was restarted for forced recirculation. The reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. In addition, Technical Specification 3.8.1.1, Action C requires a four hour report for the concurrent inoperability of the Unit 4 startup transformer to Unit 3 via the 3A 4kV bus and the Unit 3 3A diesel generator.</br>The NRC Senior Resident Inspector will be notified.</br>* * * UPDATE ON 3/18/2017 AT 1854 EDT FROM JAMES SPICHER TO BETHANY CECERE * * *</br>Update to previous report (EN 52623) to include additional reporting criteria.</br>On 3/18/17 at 1107 (EDT) the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. The 3A Emergency Diesel Generator (EDG) started on the loss of power signal but did not load, as designed, due to the bus fault. The 3A EDG was manually stopped at 1332. The Auxiliary Feedwater (AFW) System also initiated as expected. AFW was stopped at 1135. The actuations of the 3A EDG and AFW are reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A).</br>A loss of safety function affecting Units 3 and 4 occurred due to the loss of the 3A high head safety injection (HHSI) pump because it could not be powered from the faulted 3A 4kV bus with both Unit 4 HHSI pumps earlier (0624) removed from service due to planned maintenance. This caused three of the four HHSI pumps to be inoperable. The four HHSI pumps are shared by both Units 3 and 4. The safety function is achieved by two of the four HHSI pumps. Both Unit 4 HHSI pumps were restored to operable status at 1336. The loss of safety function is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D).</br>The Unit 3 reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. Unit 4 remains operating at 100% power.</br>The licensee will notify the NRC Resident Inspector.</br>Notified R2DO (Ehrhardt) and NRR EO (Miller).ified R2DO (Ehrhardt) and NRR EO (Miller).  
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +, ENS 52623 +  and ENS 52623 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 18 March 2017  +
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>.
01:43:11, 2 March 2018  +
NRC officer
Mark Abramovitz +
Notification date
15:07:00, 18 March 2017  +
Originated by
Paul Czaya +
Person
Bethany Cecere +
Power source
4kV +
Reactor critical
true  +
Reactor type
Westinghouse PWR 3-Loop +
Region
NRC Region 2 +
Reporting criterion
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +  and 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +
Reporting time
0 d (0 hours, 0 weeks, 0 months)  +
Site
Turkey Point +
Start date
15:07:00, 18 March 2017  +
State
Florida +
System
Emergency Diesel Generator +  and Auxiliary Feedwater +
TS
TS-3.8.1.1 +
Title
Reactor Trip and Loss of Ability for Unit 4 to Supply Power to Unit 3  +
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/2017/20170320en.html#en52623  +
Unit
3  +
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