ENS 50032: Difference between revisions

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| event date = 04/13/2014 21:13 EDT
| event date = 04/13/2014 21:13 EDT
| last update date = 04/14/2014
| last update date = 04/14/2014
| title = Reactor Trip Due To Actuation Of Main Generator Protection Relay
| title = Reactor Trip Due to Actuation of Main Generator Protection Relay
| event text = This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater system actuation.  The automatic trip was initiated from a generator protection relay.  A walkdown of the main generator and all protection circuitry has been completed with no visible problems identified.  A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation.  11, 12, and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip.  All control rods inserted on the reactor trip.  All ECCS and ESF systems functioned as expected.
| event text = This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater system actuation.  The automatic trip was initiated from a generator protection relay.  A walkdown of the main generator and all protection circuitry has been completed with no visible problems identified.  A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation.  11, 12, and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip.  All control rods inserted on the reactor trip.  All ECCS and ESF systems functioned as expected.
Salem Unit 1 is currently in Mode 3.  Reactor Coolant System pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dumps and Auxiliary Feedwater Systems.
Salem Unit 1 is currently in Mode 3.  Reactor Coolant System pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dumps and Auxiliary Feedwater Systems.

Latest revision as of 21:51, 1 March 2018

ENS 50032 +/-
Where
Salem PSEG icon.png
New Jersey (NRC Region 1)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-1.4 h-0.0583 days <br />-0.00833 weeks <br />-0.00192 months <br />)
Opened: William Muffley
23:49 Apr 13, 2014
NRC Officer: Donald Norwood
Last Updated: Apr 14, 2014
50032 - NRC Website
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