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ENS 40628
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Category
ENS Notification  and Power Reactor
CFR
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 +  and 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +
Current power
0  +
Current reactor mode
Hot Standby +
Description
On March 30, 2004, while at power, VCSNS ( … 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.</br>At 1129 hours, a pressure boundary leak was identified at the seal injection line to reactor coolant pump 'C'. </br>Pursuant to TS 3.4.6.2, Action a., VCSNS commenced a controlled reactor shutdown at 1410 on March 30, 2004. </br>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.</br>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.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector.  +
Discovered date
16:29:00, 30 March 2004  +
ENS id number
40,628  +
Emergency class
Non Emergency +
Entered date
17:38:00, 30 March 2004  +
Equipment trip
Turbine Trip +
Event date
16:29:00, 30 March 2004  +
Event description
On March 30, 2004, while at power, VCSNS ( … 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.</br>At 1129 hours, a pressure boundary leak was identified at the seal injection line to reactor coolant pump 'C'. </br>Pursuant to TS 3.4.6.2, Action a., VCSNS commenced a controlled reactor shutdown at 1410 on March 30, 2004. </br>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.</br>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.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector.  +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +, ENS 40628 +  and ENS 40628 +
Hours
0.0131 d (0.314 hours, 0.00187 weeks, 4.295845e-4 months)  +
Initial power
10  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 30 March 2004  +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
02:23:52, 2 March 2018  +
NRC officer
Arlon Costa +
Notification date
17:38:00, 30 March 2004  +
Originated by
Robert Sweet +
Reactor critical
true  +
Reactor type
Westinghouse PWR 3-Loop +
Region
NRC Region 2 +
Reporting criterion
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 +  and 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +
Reporting time
0.0479 d (1.15 hours, 0.00685 weeks, 0.00158 months)  +
Scram
Automatic Scram +
Site
Summer +
Start date
16:29:00, 30 March 2004  +
State
South Carolina +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Turbine +  and Control Rod +
TS
TS-3.4.6.2 +
Title
Automatic Reactor Trip Due to Lo-Lo Steam Generator Level  +
Topic
Unidentified leakage +  and Pressure boundary leak +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2004/20040331en.html#en40628  +
Unit
1  +
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