ENS 41094
ENS Event | |
|---|---|
17:34 Oct 5, 2004 | |
| Title | Inadvertent Undervoltage Condition Initated Diesel Load Sequencer, Etc. Diesel Did Not Start. |
| Event Description | At approximately 1334, during realignment from monthly surveillance testing of the normal and alternate power
supply breakers to the 10 A404 vital 4 Kv bus, an inadvertent undervoltage condition appears to have occurred. This condition resulted in initiation of the diesel load sequencer and tripping of the normal loads supplied by this bus. The undervoltage condition was momentary in nature, the load sequencer stopped upon restoration of voltage prior to starting the emergency diesel generator and operators successfully restarted the equipment that had tripped and restored the load sequencer. The D Emergency Diesel Generator is considered to be operable at this time. The cause of the occurrence is under investigation. The plant is stable in Operational Condition 1 at 100% power. This event is being reported in accordance with 10CFR50.72(b)(3)(iv)(A) 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) subsection 8', specifically in this case, Emergency ac electrical power systems." LAC Township notified by licensee. The NRC Resident Inspector was notified of this event by the licensee.
Upon further review this event was determined to not meet the reportability requirements of 10CFR50.72. The event that caused the momentary interruption to the 10A404 vital bus (i.e., less then a second) did not result in an actuation of a listed system (Emergency ac electrical power systems, including: Emergency diesel generators (EDGs)). Because the event did not meet the NUREG 1022 reporting requirement specified in 10CFR50.72 (b)(3)(iv)(A) it has been determine to not be reportable." The NRC Resident Inspector was notified of this event by the licensee. LAC Township notified by licensee. Notified R1DO (Dimitriadis) |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+1.23 h0.0513 days <br />0.00732 weeks <br />0.00168 months <br />) | |
| Opened: | Rita Braddick 18:48 Oct 5, 2004 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Nov 25, 2004 |
| 41094 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 541982019-08-03T23:47:0003 August 2019 23:47:00
[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 Trip and Manual Actuation of Reactor Core Isolation Cooling ENS 523472016-11-05T08:04:0005 November 2016 08:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Rps While Reactor Shutdown ENS 496082013-12-05T08:25:0005 December 2013 08:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Following Turbine Trip on High Moisture Separator Level ENS 491082013-06-12T17:33:00012 June 2013 17:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Circulating Water Pump Trip Leads to Reactor Scram ENS 450162009-04-23T13:10:00023 April 2009 13:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Auto Load Sequencer During Fast Bus Transfer Testing ENS 437532007-10-29T02:03:00029 October 2007 02:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Refuel Floor Exhaust Hi-Hi Radiation Alarms During Reactor Reassembly ENS 433952007-05-29T12:35:00029 May 2007 12:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to Loss of Feed Pumps After Electrical Transient ENS 411102004-10-11T01:53:00011 October 2004 01:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Rps Actuation Signal Occurred Due to Low Reactor Water Level While in Mode 3 ENS 411092004-10-10T22:14:00010 October 2004 22:14:00 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 Manual Reactor Scram Due to a Steam Leak in the Turbine Building ENS 410942004-10-05T17:34:0005 October 2004 17:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Undervoltage Condition Initated Diesel Load Sequencer, Etc. Diesel Did Not Start. ENS 403782003-12-06T04:49:0006 December 2003 04:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Level 3 Low Reactor Water Level Was Reached During a Reactor Water Level Transient 2019-08-03T23:47:00 | |