ENS 41187: Difference between revisions

v t e ENS Event
04:39 Nov 10, 2004
Title	Actuation of the Emergency Ac Electric Power System
Event Description	On November 9, 2004 at 2339 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.899895e-4 months <br />, an actuation of the emergency AC electrical power system occurred. While in a refueling outage a planned evolution was in progress to tie 480V Bus 3A to 480V Bus 6A using the tie breaker. A Bus under-voltage condition occurred when the Normal supply breaker was opened to bus 6A. When the normal supply breaker was opened, the tie breaker also opened causing a loss of power to bus 6A. With bus 6A deenergized an under-voltage signal was generated. 21 and 22 Emergency Diesel Generators automatically started and supplied bus sections 5A, 2A, and 3A. 480V Bus 6A remained deenergized because 23 Emergency Diesel Generator was out of service for planned maintenance. As a result, Residual Heat Removal cooling was lost for 5 minutes until power was restored and 21 Residual Heat Removal Pump was started. In addition, normal Spent Fuel Pool Cooling was lost for 39 minutes until 21 Spent Fuel Pool Pump was started. An activity is in progress to determine why the tie breaker opened when the normal supply breaker to Bus 6A was opened. On November 10, 2004 at 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> unit 2 was returned to its normal 480V lineup. At the time of the event, refueling outage 16 was in progress on Unit 2 with all fuel assemblies installed in the core after refueling with the Reactor Vessel Head and Upper Internals removed. This results in a condition that resulted in a valid actuation of the emergency AC electrical power systems which is reportable under 10 CFR 50.72(b)(3)(iv)(A). The loss of the 21 spent fuel pool cooling pump resulted in a 3 degree rise in spent fuel pit temperature. The loss of the 21 RHR pump resulted in no appreciable increase in reactor coolant temperature. The licensee will be notifying the New York Public Service Commission of this incident and has notified the NRC Resident Inspector.

ENS 41187 +/-
Where
Indian Point New York (NRC Region 1)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.57 h-0.0238 days <br />-0.00339 weeks <br />-7.80786e-4 months <br />)
Opened:	T.R. Jones 04:05 Nov 10, 2004
NRC Officer:	Howie Crouch
Last Updated:	Nov 10, 2004
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v • d • e

v t e Emergency Notification System
Indian Point with 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2019-03-24T18:45:00 [Table view]
[ENS list for Indian Point]

@@ Line 16: / Line 16: @@
 | event date = 11/09/2004 23:39 EST
 | last update date = 11/10/2004
-| title = Actuation Of The Emergency Ac Electric Power System
+| title = Actuation of the Emergency Ac Electric Power System
 | event text = On November 9, 2004 at 2339 hours, an actuation of the emergency AC electrical power system occurred.  While in a refueling outage a planned evolution was in progress to tie 480V Bus 3A to 480V Bus 6A using the tie breaker.  A Bus under-voltage condition occurred when the Normal supply breaker was opened to bus 6A.  When the normal supply breaker was opened, the tie breaker also opened causing a loss of power to bus 6A. With bus 6A deenergized an under-voltage signal was generated.  21 and 22 Emergency Diesel Generators automatically started and supplied bus sections 5A, 2A, and 3A.  480V Bus 6A remained deenergized because 23 Emergency Diesel Generator was out of service for planned maintenance.  As a result, Residual Heat Removal cooling was lost for 5 minutes until power was restored and 21 Residual Heat Removal Pump was started.  In addition, normal Spent Fuel Pool Cooling was lost for 39 minutes until 21 Spent Fuel Pool Pump was started.  An activity is in progress to determine why the tie breaker opened when the normal supply breaker to Bus 6A was opened.
 On November 10, 2004 at 0058 hours unit 2 was returned to its normal 480V lineup.

v t e Unit 2
W-4-LP
Reactor critical	Not Critical
Scram	No
Before	Refueling (0 %)
After	Refueling (0 %)

ENS 41187: Difference between revisions

Latest revision as of 21:22, 1 March 2018

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ENS 41187: Difference between revisions

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