ENS 44735
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ENS Event | |
|---|---|
23:31 Dec 19, 2008 | |
| Title | Automatic Reactor Scram Due to Load Reject |
| Event Description | On December 19, 2008, at 1831 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.966955e-4 months <br /> with the reactor at 100% core thermal power (CTP) an automatic reactor scram occurred. It appears the scram occurred as a result of a load reject experienced during a severe winter storm. Three of the four safety relief valves opened in response to the event. Primary Containment Isolation System (PCIS) Group 2 (sample valves) and Group 6 (reactor water cleanup system) and the reactor building isolation system (RBIS-secondary containment) isolated as designed (all have since been restored) on the reactor water level +12 inches setpoint due to normal vessel shrink. Initial review indicates all safety-related systems responded as designed. Off-site power has been maintained; however the two 4kv safety related buses (A5&A6) were conservatively placed on the station emergency diesel generators due to potential grid stability concern. Currently, the reactor mode select switch (RMSS) is in the Shutdown position; the reactor scram has been reset; the reactor is being maintained at approximately 940 psig, with pressure being maintained by the main turbine by-pass valves; and reactor water level is being maintained at normal levels of 29 inches with the main condensate and feedwater system. Station maintenance personnel are assessing the status of the station switchyard. Once this activity is complete the duration of the forced outage and recovery plans will be determined.
All control rods fully inserted on the scram. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
| Pilgrim Massachusetts (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:+-1.65 h-0.0688 days <br />-0.00982 weeks <br />-0.00226 months <br />) | |
| Opened: | Bruce Chenard 21:52 Dec 19, 2008 |
| NRC Officer: | John Knoke |
| Last Updated: | Dec 19, 2008 |
| 44735 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Pilgrim with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 540712019-05-18T03:03:00018 May 2019 03:03:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Degrading Condenser Vacuum ENS 536482018-10-05T04:00:0005 October 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 Scram Due to Low Reactor Water Level ENS 531472018-01-04T19:10:0004 January 2018 19:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Partial Loss of Offsite Power During Winter Storm ENS 522232016-09-06T12:27:0006 September 2016 12:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to High Reactor Water Level ENS 513382015-08-22T20:28:00022 August 2015 20:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to a Single Msiv Closure ENS 510872015-05-22T14:02:00022 May 2015 14:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Condenser Vacuum ENS 507692015-01-27T09:02:00027 January 2015 09:02:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram on Turbine Trip Due to Loss of Offsite Power ENS 494542013-10-19T07:31:00019 October 2013 07:31:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Group 1 Isolation Due to High Reactor Water Level ENS 492962013-08-22T11:55:00022 August 2013 11:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Reactor Protection Actuation (Scram) ENS 489232013-04-15T02:17:00015 April 2013 02:17:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuations While Shutting Down ENS 487392013-02-10T19:05:00010 February 2013 19:05:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power and Subsequent Press Release ENS 487362013-02-09T03:00:0009 February 2013 03:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Loss of Offsite Power ENS 486642013-01-10T20:34:00010 January 2013 20:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Protection Actuation (Scram) - Recirculation Pump Trip ENS 479452012-05-22T17:11:00022 May 2012 17:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Degrading Condenser Vacuum ENS 468372011-05-10T17:15:00010 May 2011 17:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Protection System Actuation During Start-Up ENS 466312011-02-20T15:34:00020 February 2011 15:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Protection System Actuation While Shutdown ENS 447372008-12-20T15:45:00020 December 2008 15:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Momentary Loss of 345Kv Offsite Power ENS 447352008-12-19T23:31:00019 December 2008 23:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Load Reject ENS 434792007-07-10T23:54:00010 July 2007 23:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Main Turbine Trip Causing a Reactor Scram ENS 432452007-03-17T20:58:00017 March 2007 20:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Group Isolations Following Manual Reactor Scram ENS 424142006-03-13T23:08:00013 March 2006 23:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram After Offgas System Failure 2019-05-18T03:03:00 | |
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