ENS 50550: Difference between revisions

v t e ENS Event
00:51 Oct 20, 2014
Title	Manual Reactor Trip Resulting in Aux Feedwater Actuation
Event Description	This is an 8-hour notification being made to report that a valid ESF [emergency safety features] auxiliary feed water system actuation occurred. Salem Unit 1 was in mode 1 at 19% reactor power and executed a planned manual reactor trip to begin a scheduled refueling outage (1R23). The 11, 12, and 13 AFW [auxiliary feedwater] pumps were not in service prior to the reactor trip and as a result, narrow range levels in 12, 13, and 14 steam generators reached 14% before recovering. This resulted in a valid ESF actuation for low steam generator water level. Steam generator water levels were restored to normal post trip values as part of the procedurally directed response to a reactor trip. All safety related equipment was operational before the reactor trip and AFW actuation and responded as required. There were no equipment failures that contributed to this event. There were no personnel injuries as a result of' this event. The NRC Resident Inspector has been informed. A transformer alarm caused the operators to trip the reactor prior to reaching the step in the procedure to start the AFW pumps. * * UPDATE FROM JOHN OSBORNE TO DONALD NORWOOD AT 1555 EST ON 11/24/2014 * * * On October 20, 2014 at 0136 EDT, Salem Unit 1 reported an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification of a valid ESF Auxiliary Feed Water System actuation following a manual reactor trip at the start of the S1R23 refueling outage. After additional review it was determined that the manual reactor trip met the criteria for a four hour report in accordance with 10CFR50.72(b)(2)(iv)(B), 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical...'. The licensee notified the NRC Resident Inspector. Notified R1DO (Noggle).

ENS 50550 +/-
Where
Salem New Jersey (NRC Region 1)
Reporting

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+0.75 h0.0313 days <br />0.00446 weeks <br />0.00103 months <br />)
Opened:	Dan Mchugh 01:36 Oct 20, 2014
NRC Officer:	Mark Abramovitz
Last Updated:	Nov 24, 2014
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v • d • e

v t e Emergency Notification System
Salem with 10 CFR 50.72(b)(3)(iv)(A), System Actuation
WEEKMONTHYEAR2022-12-24T07:22:00 [Table view]
[ENS list for Salem]

@@ Line 16: / Line 16: @@
 | event date = 10/19/2014 20:51 EDT
 | last update date = 11/24/2014
-| title = Manual Reactor Trip Resulting In Aux Feedwater Actuation
+| title = Manual Reactor Trip Resulting in Aux Feedwater Actuation
 | event text = This is an 8-hour notification being made to report that a valid ESF [emergency safety features] auxiliary feed water system actuation occurred.  Salem Unit 1 was in mode 1 at 19% reactor power and executed a planned manual reactor trip to begin a scheduled refueling outage (1R23).  The 11, 12, and 13 AFW [auxiliary feedwater] pumps were not in service prior to the reactor trip and as a result, narrow range levels in 12, 13, and 14 steam generators reached 14% before recovering.  This resulted in a valid ESF actuation for low steam generator water level.  Steam generator water levels were restored to normal post trip values as part of the procedurally directed response to a reactor trip.
 All safety related equipment was operational before the reactor trip and AFW actuation and responded as required.  There were no equipment failures that contributed to this event.  There were no personnel injuries as a result of' this event.

v t e Unit 1
W-4-LP
Reactor critical	Critical
Scram	No
Before	Power Operation (19 %)
After	Hot Standby (0 %)

ENS 50550: Difference between revisions

Latest revision as of 20:49, 1 March 2018

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ENS 50550: Difference between revisions

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