ENS 43329
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ENS Event | |
|---|---|
19:02 Apr 30, 2007 | |
| Title | Reactor Trip Due to Grass Intrusion Into Circulating Water Intake Structure |
| Event Description | {{#Wiki_filter:A manual trip of Salem Unit 1 was initiated due to a loss of the circulators from heavy grassing at the circulating water intake structure. All rods fully inserted on the trip and all systems responded as designed, with decay heat being removed via the atmospheric relief valves and subsequently the steam dump system. All Auxiliary Feedwater pumps auto started as expected on low steam generator levels from the trip. Salem Unit 1 had entered the abnormal operating procedure for circulating water due to two (2) circulators being out of service; one circulator previously emergency tripped due to excessive traveling water screen [differential pressure] and a second circulator emergency tripped soon thereafter. The procedure provides guidance to trip the plant if less than three (3) circulators are in service and power is above ten (10) percent. Two (2) of the remaining four (4) in-service circulators emergency tripped due to excessive traveling water screen differential pressure. At this point the manual reactor trip was initiated. The crew entered emergency operating procedures and stabilized the plant at no load conditions.
No personnel injuries have occurred as a result of the trip. Salem Unit 2 was not affected and is operating at 100% power. Salem Unit 1 is currently in Mode 3. Reactor Coolant System temperature is 547� F with pressure at 2235 psig. All ECCS and ESF Systems are available. Actions are being taken to return circulators to service. The licensee notified the NRC Resident Inspector. }}[[Event description::Description::{{#Regex_clear:A manual trip of Salem Unit 1 was initiated due to a loss of the circulators from heavy grassing at the circulating water intake structure. All rods fully inserted on the trip and all systems responded as designed, with decay heat being removed via the atmospheric relief valves and subsequently the steam dump system. All Auxiliary Feedwater pumps auto started as expected on low steam generator levels from the trip. Salem Unit 1 had entered the abnormal operating procedure for circulating water due to two (2) circulators being out of service; one circulator previously emergency tripped due to excessive traveling water screen [differential pressure] and a second circulator emergency tripped soon thereafter. The procedure provides guidance to trip the plant if less than three (3) circulators are in service and power is above ten (10) percent. Two (2) of the remaining four (4) in-service circulators emergency tripped due to excessive traveling water screen differential pressure. At this point the manual reactor trip was initiated. The crew entered emergency operating procedures and stabilized the plant at no load conditions. No personnel injuries have occurred as a result of the trip. Salem Unit 2 was not affected and is operating at 100% power. Salem Unit 1 is currently in Mode 3. Reactor Coolant System temperature is 547� F with pressure at 2235 psig. All ECCS and ESF Systems are available. Actions are being taken to return circulators to service. The licensee notified the NRC Resident Inspector. }}| ]] |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-2.22 h-0.0925 days <br />-0.0132 weeks <br />-0.00304 months <br />) | |
| Opened: | Richard Desanctis 16:49 Apr 30, 2007 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Apr 30, 2007 |
| 43329 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (80 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 562862022-12-24T07:22:00024 December 2022 07:22:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 546072020-03-25T04:56:00025 March 2020 04:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Failure of a Rod Control Motor Generator ENS 542112019-08-11T12:14:00011 August 2019 12:14:00 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 Feedwater Regulating Valve Malfunction ENS 538522019-01-31T08:01:00031 January 2019 08:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip - Circulating Water Icing Conditions ENS 536062018-09-14T04:00:00014 September 2018 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 a Failure of the Steam Generator Feed Regulating Valve ENS 533862018-05-07T07:25:0007 May 2018 07:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 522132016-08-31T19:11:00031 August 2016 19:11:00 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 Reactor Coolant Flow ENS 520482016-06-28T08:23:00028 June 2016 08:23:00 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 Main Generator Protection Signal ENS 517342016-02-15T01:58:00015 February 2016 01:58:00 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 Main Generator Protection Trip ENS 517082016-02-04T16:21:0004 February 2016 16:21:00 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 Main Turbine Trip ENS 512902015-08-05T19:38:0005 August 2015 19:38:00 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 Reactor Coolant Flow ENS 500922014-05-07T08:56:0007 May 2014 08:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to Generator Protection Relay ENS 500322014-04-14T01:13:00014 April 2014 01:13:00 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 Actuation of Main Generator Protection Relay ENS 500122014-04-09T01:14:0009 April 2014 01:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped Following the Loss of an Operating Steam Generator Feed Pump (Sgfp) ENS 497802014-01-31T15:01:00031 January 2014 15:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 486172012-12-21T10:28:00021 December 2012 10:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip on Turbine Trip ENS 485342012-11-25T16:30:00025 November 2012 16:30:00 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 Steam Generator Feedwater Regulator Valve Not Responding to Demand Signal ENS 484572012-10-30T05:09:00030 October 2012 05:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip from 100% Power ENS 478742012-04-30T14:18:00030 April 2012 14:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - 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 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 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 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 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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