ENS 44647
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ENS Event | |
|---|---|
16:08 Nov 9, 2008 | |
| Title | Manual Reactor Scram Due to Spurious Srv Opening |
| Event Description | One hour reportable event based on a safety relief valve (SRV) failure to close (NUREG 0626 and NUREG 0660).
On 11/09/08 at approximately 11:08 with Unit 2 at 100% steady state power SRV 2-B21-F013H spuriously failed full open with no operator action or testing in progress. The valve's control switch was cycled as required by Abnormal Operating Procedure AOP-30 with no success. At 1113 the valve was successfully closed by pulling the associated fuses. At 1117, a manual reactor scram was inserted based on a Torus temperature of 109.8 degrees F (Technical Specifications require a scram to be inserted at 110 degrees F). All control rods [fully] inserted from the manual scram signal. Reactor water level lowered to Low Level 2 resulting in Primary Containment Isolation System (PCIS) isolations of Groups 2, 3, 6, and 8. In addition, this resulted in a Reactor Core Isolation Cooling (RCIC) system actuation and injection into the reactor. The High Pressure Coolant Injection (HPCI) system actuated but did not inject because reactor water level recovered. An Alternate Rod Insertion signal was received, the Standby Gas Treatment (SBGT) system initiated, and the Reactor Recirculation Pumps tripped as designed. Plant safety systems responded as designed to the transient. [Licensee] investigations are underway to determine the cause of the SRV failure. Reactor decay heat is being removed through the main turbine bypass valves to the condenser. Reactor make-up is being maintained by the normal feedwater system. The plant is in its normal shutdown electrical lineup supplied by offsite power. The diesel generators are available for service to the plant The Licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| Other Unspec Reqmnt 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-4 h-0.167 days <br />-0.0238 weeks <br />-0.00548 months <br />) | |
| Opened: | Curtis Dunmore 12:08 Nov 9, 2008 |
| NRC Officer: | Vince Klco |
| Last Updated: | Nov 9, 2008 |
| 44647 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Brunswick with Other Unspec Reqmnt, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 576362025-03-28T18:09:00028 March 2025 18:09:00
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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 2025-03-28T18:09:00 | |
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