ENS 48457
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ENS Event | |
|---|---|
05:09 Oct 30, 2012 | |
| Title | Manual Reactor Trip from 100% Power |
| Event Description | This report if being made under the requirements of 10 CFR 50.72(b)(2)(iv)(B), Actuation of the Reactor Protection System While Critical, except preplanned, and under the requirements of 10 CFR 50.72(b)(3)(iv)(A), Valid Actuation of Listed System, except preplanned.
Salem Unit 1 was operating at 100% reactor power when a loss of 4 condenser circulators required a manual reactor trip in accordance with station procedures. The cause of the 4 circulators being removed from service was due to a combination of high river level and detritus from Hurricane Sandy's transit. All control rods inserted. A subsequent loss of the 2 remaining circulators required transition of decay heat removal from condenser steam dumps to the 11-14 MS10s (atmospheric steam dump). Decay heat removal is from the 11/12 Aux Feed Pumps to all 4 steam generators via the 11-14 MS10s. 11/12/13 AFW pumps started due to low level on all steam generators due to shrink from full power operation (this is a normal response). All safety related equipment functioned as expected. No one has been injured. As an additional note, Hurricane Sandy had recently moved past artificial island. Salem Unit 1 is currently in Mode 3. Salem Unit 2 reactor is currently in its 2R19 refueling outage and is shutdown and defueled with no fuel movement in progress. The licensee has notified the NRC Resident Inspector.
At 0513, following [a] Unit 1 manual [reactor] trip due to loss of condenser cooling, a manual steam line isolation was initiated due to a high condenser back pressure. All main steamline isolation valves responded as expected. The high condenser back pressure resulted in the #11 low pressure turbine rupture disc relieving. Unit 1 remains in mode 3 with Reactor Coolant System temperature at 549 [degrees] and stable. Reactor Coolant System pressure is 2235 psig and in automatic control. Pressurizer level is on program at 26 percent level and in automatic control. Core cooling is via aux feed water and the steam generator levels are on program. There were no [personnel] injuries. The licensee has notified the NRC Resident Inspector. Notified R1DO (Caruso). |
| Where | |
|---|---|
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:+-0.98 h-0.0408 days <br />-0.00583 weeks <br />-0.00134 months <br />) | |
| Opened: | John Brennan 04:10 Oct 30, 2012 |
| NRC Officer: | Eric Simpson |
| Last Updated: | Oct 30, 2012 |
| 48457 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| 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 | |
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