ENS 42004
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ENS Event | |
|---|---|
03:40 Sep 21, 2005 | |
| Title | Technical Specification Required Shutdown Commenced Due to Inoperability of Residual Heat Removal Containment Sump Isolation Valves |
| Event Description | At 2240 09/20/2005 an engineering evaluation concluded that the Residual Heat Removal Containment Sump Isolation Valves were inoperable based on their inability to open against a higher differential pressure than had been previously evaluated. Historically Wolf Creek has operated with the Component Cooling Water isolated to the Residual Heat Removal Heat Exchangers. If the pumps started during accident conditions there is a potential that the pump heat generated could cause system pressure to increase to the suction relief valve setting of 450 psig. Testing of the valves has shown that they are capable of opening with 207 psid across the valve.
Technical Specification 3.0.3 was entered at 2240 9/20/2005 due to the inoperability of both Residual Heat Removal trains. Power reduction was commenced at 2340. Component Cooling Water was aligned to the Residual Heat Removal Heat Exchangers at 0004 9/21/2005 restoring operability of the Residual Heat Removal trains. At 0017 9/21/2005 actions were commenced to restore power to 100%. This event is reportable under 10 CFR50.72(b)(2)(i) Technical Specification required shut down (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and 10 CFR50.72(b)(3)(v)(B) Event or Condition that could have prevented fulfillment of a Safety Function (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). The NRC Resident has been contacted.
Evaluation of the Residual Heat Removal Containment Sump Isolation Valves concluded that the valves were operable and the Residual Heat Removal trains were capable of fulfilling their safety function. Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(B). The licensee notified the NRC Resident Inspector. Notified the R4DO (Whitten). |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+-1.05 h-0.0438 days <br />-0.00625 weeks <br />-0.00144 months <br />) | |
| Opened: | Dave Dees 02:37 Sep 21, 2005 |
| NRC Officer: | Arlon Costa |
| Last Updated: | Nov 8, 2005 |
| 42004 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Wolf Creek with 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 545082020-02-02T00:45:0002 February 2020 00:45:00
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Spec. Required Shutdown Due to Gas Voiding in Discharge Piping ENS 438922008-01-11T00:12:00011 January 2008 00:12:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Voiding Discovered in High Head and Intermediate Head Si Common Suction ENS 420292005-09-30T14:45:00030 September 2005 14:45:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Vulnerabilities Discovered During Design Basis Fire Review ENS 420042005-09-21T03:40:00021 September 2005 03:40:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Commenced Due to Inoperability of Residual Heat Removal Containment Sump Isolation Valves ENS 405962004-03-17T20:57:00017 March 2004 20:57:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Switchgear Rooms Flooding Analysis Concerns 2020-02-02T00:45:00 | |
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