ENS 40628
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ENS Event | |
|---|---|
16:29 Mar 30, 2004 | |
| Title | Automatic Reactor Trip Due to Lo-Lo Steam Generator Level |
| Event Description | On March 30, 2004, while at power, VCSNS [V.C. Summer Nuclear Station] personnel were performing a reactor building inspection to identify the source of reactor coolant system unidentified leakage that was within Technical Specification (TS) limits.
At 1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br />, a pressure boundary leak was identified at the seal injection line to reactor coolant pump 'C'. Pursuant to TS 3.4.6.2, Action a., VCSNS commenced a controlled reactor shutdown at 1410 on March 30, 2004. During the shutdown, the main turbine experienced higher than normal vibration. At 1516, the turbine was manually tripped at approximately 43% reactor power. Subsequent to the turbine trip, feedwater regulating valve IFV-498 failed in the closed position while in automatic with a full open demand signal. The cause of this failure is not known. The reactor automatically tripped at 1520 due to lo-lo level in the 'C' steam generator at 10% reactor power. All control rods fully inserted and all safety systems responded normally. Both motor driven emergency feedwater pumps started as required. The plant stabilized in mode 3. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Summer  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000395/LER-2004-001 |
| Time - Person (Reporting Time:+1.15 h0.0479 days <br />0.00685 weeks <br />0.00158 months <br />) | |
| Opened: | Robert Sweet 17:38 Mar 30, 2004 |
| NRC Officer: | Arlon Costa |
| Last Updated: | Mar 30, 2004 |
| 40628 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (10 %) |
| After | Hot Standby (0 %) |
Summer with 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 569782024-02-19T07:36:00019 February 2024 07:36:00
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ENS 429982006-11-09T19:44:0009 November 2006 19:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation During Testing ENS 429152006-10-17T18:15:00017 October 2006 18:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified During an Outage ENS 417062005-05-18T05:54:00018 May 2005 05:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Balance of Plant Power Due to Transformers Lockout ENS 408112004-06-13T00:29:00013 June 2004 00:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Started and Loaded on Bus Undervoltage Signal ENS 406282004-03-30T16:29:00030 March 2004 16:29:00 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Automatic Reactor Trip Due to Lo-Lo Steam Generator Level ENS 403482003-11-21T14:10:00021 November 2003 14:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Bank "C" Rods Tripped Due to Incorrect Digital Rod Position Indication (Drpi) ENS 402612003-10-20T11:00:00020 October 2003 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Through-Wall Leakage Found on Seal Injection Piping 2024-02-19T07:36:00 | |
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