ENS 45604
ENS Event | |
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13:04 Jan 3, 2010 | |
Title | Manual Reactor Trip Due To Loss Of Circulators After Uptake Of River Ice |
Event Description | A manual trip of Salem Unit 2 was initiated due to a loss of 4 circulators due to an excessive uptake of river ice. Strong northwest winds, freezing temperatures and abnormally low tide levels contributed to the ice formation on the river. The operating crew entered EOP-TRIP-A, appropriately transitioned to EOP-TRIP-2 and stabilized the plant at no load conditions (MODE 3 Hot Stand-by).
All rods fully inserted on the trip and all systems responded as designed with decay heat being removed via the Steam Dump system, with condenser vacuum maintained. All three AFW Pumps auto started due to low Steam Generator level due to closure of 21-23CN27, low pressure feed water heater inlet isolation valves. There were no other significant equipment challenges associated with the reactor trip. Salem Unit-2 is currently in mode 3. The Reactor Coolant System temperature is 547 [degrees] F with pressure at 2235 psig [NOT and NOP]. All ECCS and ESF Systems are available and no ECCS systems actuated during the event. No personnel injuries occurred as a result of the trip. [The Unit 2 reactor trip recovery is uncomplicated.]. Unit 1 power was also reduced to 80%. Although the combination of strong northwest winds, freezing temperatures and an abnormally low tide contributed to the ice formation on the river, operators foresee no further complication due to the ice conditions. The licensee has notified the NRC Resident Inspector and will notify the States of Delaware and New Jersey. |
Where | |
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Salem 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:+-1.2 h-0.05 days <br />-0.00714 weeks <br />-0.00164 months <br />) | |
Opened: | Enricas Villar 11:52 Jan 3, 2010 |
NRC Officer: | Vince Klco |
Last Updated: | Jan 3, 2010 |
45604 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (82 %) |
After | Hot Standby (0 %) |
Salem with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 562862022-12-24T07:22:00024 December 2022 07:22:00
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ECCS Discharge Unusual Event Due to a Potential Fire in Containment ENS 477662012-03-23T18:28:00023 March 2012 18:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Followed by Automatic Reactor Trip ENS 469922011-06-26T04:00:00026 June 2011 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of Reactor Coolant Pump ENS 467742011-04-21T20:01:00021 April 2011 20:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Circulating Water Pumps Out of Service ENS 463372010-10-17T09:12:00017 October 2010 09:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to 4 Kv Group Bus Undervoltage Condition ENS 463362010-10-16T03:21:00016 October 2010 03:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Turbine Trip ENS 460752010-07-07T15:17:0007 July 2010 15:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Main Generator and Turbine Trip ENS 458482010-04-16T20:41:00016 April 2010 20:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Generator Start Due to Loss of a 4160 V Bus ENS 456472010-01-21T23:20:00021 January 2010 23:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Low Steam Generator Water Level ENS 456042010-01-03T13:04:0003 January 2010 13:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Circulators After Uptake of River Ice ENS 446292008-11-05T05:57:0005 November 2008 05:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Start Due to Unexpected Esf Signal ENS 438732007-12-28T22:54:00028 December 2007 22:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip on Failure of Station Power Transformer ENS 435502007-08-06T17:10:0006 August 2007 17:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Spurious Interlock Signal to Feedwater Regulating Valves ENS 433822007-05-24T06:32:00024 May 2007 06:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 433292007-04-30T19:02:00030 April 2007 19:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Grass Intrusion Into Circulating Water Intake Structure ENS 433172007-04-25T02:48:00025 April 2007 02:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Circulators ENS 432592007-03-28T00:50:00028 March 2007 00:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Low Steam Generator Water Level Initiated Auxiliary Feedwater Signal and a Reactor Trip Signal ENS 429462006-10-30T01:11:00030 October 2006 01:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Auxiliary Feedwater During Msiv Testing ENS 428642006-09-26T19:13:00026 September 2006 19:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Reactor Coolant Pump Seal Leakage. ENS 423952006-03-08T16:09:0008 March 2006 16:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip as a Result of a Turbine Generator Trip ENS 410282004-09-09T05:06:0009 September 2004 05:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Turbine Trip/Reactor Trip ENS 408752004-07-15T23:44:00015 July 2004 23:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip from 8% Power Due to Lowering Water Level on 23 Steam Generator ENS 408652004-07-13T17:05:00013 July 2004 17:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Low Steam Generator Water Level. ENS 406652004-04-11T04:23:00011 April 2004 04:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Plant Had a Valid Esf Signal to Start 1C Emergency Diesel Generator ENS 406392004-04-03T15:50:0003 April 2004 15:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Auxiliary Feedwater System During Maintenance ENS 403502003-11-23T10:19:00023 November 2003 10:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Was Manually Tripped After a Control Rod Dropped During Low Power Physics ENS 397132003-03-29T09:42:00029 March 2003 09:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation 2022-12-24T07:22:00 | |