ENS 53147
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ENS Event | |
|---|---|
19:10 Jan 4, 2018 | |
| Title | Manual Reactor Scram Due to Partial Loss of Offsite Power During Winter Storm |
| Event Description | On January 4, 2018, at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br /> EST, with the reactor at approximately 100 percent power and steady state conditions, the winter storm across the Northeast caused the loss of offsite 345 kV Line 342. Reactor power was reduced to approximately 81 percent and a procedurally required manual reactor scram was initiated. All control rods fully inserted.
As a result of the reactor scram, indicated reactor water level decreased, as expected, to less than +12 inches resulting in automatic actuation of the Primary Containment Isolation Systems for Group II - Primary Containment Isolation and Reactor Building Isolation System, and Group VI - Reactor Water Cleanup System. Reactor Water Level was restored to the normal operating band. The Primary Containment Isolation Systems have been reset. The Reactor Protection System signal has been reset. Following the reactor scram, the non-safety related Control Rod Drive Pump "B" tripped on low suction pressure. Control Rod Drive Pump "A" was placed in service. All other systems operated as expected, in accordance with design. This event is reportable per the requirements of Title 10, Code of Federal Regulations (CFR) 50.72 (b)(2)(iv)(B) - "RPS Actuation" and 10 CFR 50.72 (b)(3)(iv)(A) - "Specified System Actuation. This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified. The main steam isolation valves are open with decay heat being removed via steam to the main condenser. Offsite power is still available from 345kV line 355. As a contingency, emergency diesel generators are running and powering safety busses per licensee procedure. The licensee notified the Commonwealth of Massachusetts. The licensee will be notifying the town of Plymouth as part of their local notifications. The licensee will be issuing a press release. |
| 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:+-1.22 h-0.0508 days <br />-0.00726 weeks <br />-0.00167 months <br />) | |
| Opened: | Michael Mcdonnell 17:57 Jan 4, 2018 |
| NRC Officer: | David Aird |
| Last Updated: | Jan 4, 2018 |
| 53147 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (81 %) |
| 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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