ENS 44685
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ENS Event | |
|---|---|
17:00 Nov 26, 2008 | |
| Title | Automatic Reactor Scram Due to Ehc Malfunction |
| Event Description | At 12:00 hours EST, an apparent Electro-Hydraulic Control (EHC) system malfunction while synchronizing the Main Generator to the grid resulted in a Group 1 Main Steam Isolation Valve (MSIVs) closure on low reactor pressure and a subsequent automatic reactor scram.
Preliminary investigation of the automatic scram signal indicates that Main Steam Line Low Pressure Instruments (B21-PT-N015 A thru D) sensed low steam line pressure after the Main Generator was paralleled to the grid. This resulted in the closure of all MSIVs. Closure of MSIVs in Mode 1 results in an automatic reactor scram. All control rods fully inserted. With the exception of the EHC system, all systems responded as designed. This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) due to the Reactor Protection System (RPS) actuation and 10CFR 50,72(b)(3)(iv)(A) due to the Primary Containment Isolation System (PCIS) Groups 1, 2, and 6 actuations. Unit 2 was not affected by this event and remains at 100% power. Reactor Pressure is 844 psig, reactor temperature is 526 degrees Fahrenheit. MSIV's remain shut. Decay heat was removed via MSIV bypass lines. RCIC actuated for a period of time for level control but has been secured. CRD pumps are providing makeup water. No SRV's or relief valves lifted. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000325/LER-2008-007 |
| Time - Person (Reporting Time:+-1.8 h-0.075 days <br />-0.0107 weeks <br />-0.00247 months <br />) | |
| Opened: | Dave Jester 15:12 Nov 26, 2008 |
| NRC Officer: | Joe O'Hara |
| Last Updated: | Nov 26, 2008 |
| 44685 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (22 %) |
| After | Hot Shutdown (0 %) |
Brunswick with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 569772024-02-19T04:25:00019 February 2024 04:25:00
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ECCS Discharge Reactor Scram Due to Trip from Neutron Monitoring System ENS 429862006-11-11T17:43:00011 November 2006 17:43:00 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 Conductivity Excursion ENS 429552006-11-01T23:37:0001 November 2006 23:37:00 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)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Unit 2 Declared an Unusual Event Due to Loss of Offsite Power to the 4Kv Emergency Buses ENS 418372005-07-13T13:17:00013 July 2005 13:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip/Reactor Trip ENS 415822005-04-09T05:50:0009 April 2005 05:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scrammed from 61% Power Due to Low Reactor Water Level ENS 409542004-08-14T16:59:00014 August 2004 16:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation Due to Loss of Offsite Power ENS 402972003-11-04T22:32:0004 November 2003 22:32:00 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 Brunswick Unit 2 Scram Due to Generator/Turbine Trip 2024-02-19T04:25:00 | |
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