ENS 46336: Difference between revisions

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| event date = 10/15/2010 23:21 EDT
| event date = 10/15/2010 23:21 EDT
| last update date = 10/16/2010
| last update date = 10/16/2010
| title = Automatic Reactor Trip Due To A Turbine Trip
| title = Automatic Reactor Trip Due to a Turbine Trip
| event text = An automatic reactor trip of Salem Unit 1 [occurred] due to a turbine trip above P-9.  The crew entered EOP [Emergency Operating Procedure] Trip 1, appropriately transitioned to EOP Trip 2, and stabilized the plant at no load conditions.  All rods fully inserted on the trip, and all systems responded as designed with decay heat removal being removed via the steam dump system with condenser vacuum being maintained.  The Auxiliary Feed Water Pumps automatically started due to low steam generator levels.  Salem Unit 1 is currently in Mode 3.  Reactor Coolant System temperature is 547 degrees, and pressure is 2235 pounds.  All Emergency Core Cooling Systems and Engineered Safety Function Systems are available.  No personnel injuries occurred as a result of the trip.  No radiological release [occurred] due to this event.
| event text = An automatic reactor trip of Salem Unit 1 [occurred] due to a turbine trip above P-9.  The crew entered EOP [Emergency Operating Procedure] Trip 1, appropriately transitioned to EOP Trip 2, and stabilized the plant at no load conditions.  All rods fully inserted on the trip, and all systems responded as designed with decay heat removal being removed via the steam dump system with condenser vacuum being maintained.  The Auxiliary Feed Water Pumps automatically started due to low steam generator levels.  Salem Unit 1 is currently in Mode 3.  Reactor Coolant System temperature is 547 degrees, and pressure is 2235 pounds.  All Emergency Core Cooling Systems and Engineered Safety Function Systems are available.  No personnel injuries occurred as a result of the trip.  No radiological release [occurred] due to this event.
Approximately 5 minutes prior to the turbine trip, Salem Unit 1 lowered reactive loading on the voltage regulator as requested by the load dispatcher while Hope Creek Unit 1 was coming off line due to their outage.  The cause of the trip is still under investigation.  There was no impact on Salem Unit 2 as a direct result of this event.   
Approximately 5 minutes prior to the turbine trip, Salem Unit 1 lowered reactive loading on the voltage regulator as requested by the load dispatcher while Hope Creek Unit 1 was coming off line due to their outage.  The cause of the trip is still under investigation.  There was no impact on Salem Unit 2 as a direct result of this event.   

Latest revision as of 21:08, 1 March 2018

ENS 46336 +/-
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:+-1.48 h-0.0617 days <br />-0.00881 weeks <br />-0.00203 months <br />)
Opened: Gary Meekins
01:52 Oct 16, 2010
NRC Officer: Dong Park
Last Updated: Oct 16, 2010
46336 - NRC Website
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