ENS 45724
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ENS Event | |
|---|---|
17:40 Feb 24, 2010 | |
| Title | Auxiliary Feedwater Pumps May Experience Runout at Low Steam Pressures |
| Event Description | At 1140 CST, both of the stations safety related auxiliary feedwater (AFW) pumps were declared inoperable. The AFW pumps were declared inoperable due to an evaluation that determined that the pumps may experience runout at low steam generator pressures during some design basis events. The stations Technical Specifications require that: 'With both AFW trains inoperable, then initiate actions to restore one AFW train to OPERABLE status immediately.' Technical Specification (TS) 2.0.1 and all TS actions requiring MODE change are suspended until one AFW train is restored to OPERABLE status.
The station is aggressively working to develop a solution to return at least one train of the AFW system to operability. The licensee notified the NRC Resident Inspector.
At 2133 CST, Steam Driven Auxiliary Feedwater Pump, FW-10, was declared operable based on an engineering evaluation that determined FW-10 will perform as required under all design basis conditions. Motor Driven Auxiliary Feedwater Pump, FW-6, remains inoperable. [The licensee] exited Technical Specification 2.0.1 and 2.5(1)D, and entered TS 2.5(1)B, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO, effective as of 1140 CST. The licensee notified the NRC Resident Inspector. Notified R4DO (Lantz).
At 0238 CST, Motor Driven Auxiliary Feedwater Pump, FW-6, was declared operable per an Engineering Operability Evaluation. [The licensee] exited Technical Specification 2.5(1)B. The licensee notified the NRC Resident Inspector. Notified R4DO (Lantz).
Further review has determined that the auxiliary feedwater pumps are and have been fully capable of performing their required safety function. Therefore, this notification is being retracted. The licensee notified the NRC Resident Inspector. Notified R4DO(Lantz) |
| Where | |
|---|---|
Ft Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+0.5 h0.0208 days <br />0.00298 weeks <br />6.849e-4 months <br />) | |
| Opened: | John Musser 18:10 Feb 24, 2010 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Feb 25, 2010 |
| 45724 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Fort Calhoun with 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 518072016-03-18T16:28:00018 March 2016 16:28:00
[Table view]10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Shutdown Cooling Pipe Void ENS 512702015-07-22T18:30:00022 July 2015 18:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Reactor Coolant System Leak ENS 511312015-06-05T18:30:0005 June 2015 18:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Loss of Decay Heat Removal to the 'A' Steam Generator ENS 497102014-01-10T05:17:00010 January 2014 05:17:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Fittings Connected to Containment Penetration ENS 497032014-01-09T09:15:0009 January 2014 09:15:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Intake Structure Sluice Gate Inoperable ENS 494522013-10-18T18:28:00018 October 2013 18:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential for High Energy Line Break on Letdown System Outside Containment ENS 485512012-12-02T21:30:0002 December 2012 21:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Inadequate Raw Water Pump Anchor Embedment ENS 481112012-07-17T15:00:00017 July 2012 15:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Charging Line Socket Welds Based on Thermal Fatigue Analysis ENS 479532012-05-23T21:00:00023 May 2012 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Crack Identified in Pressurizer Heater ENS 474732011-11-22T23:00:00022 November 2011 23:00:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Temporary Loss of Shutdown Cooling ENS 473592011-10-20T15:50:00020 October 2011 15:50:00 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 Flood Barrier Penetrations Not Water Tight ENS 467232011-04-04T20:00:0004 April 2011 20:00:00 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)(v)(C), Loss of Safety Function - Release of Radioactive Material Scaffolding Affecting Safety Related Equipment ENS 465952011-02-06T04:17:0006 February 2011 04:17:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Both Trains of Auxiliary Feed Water Disabled ENS 457902010-03-25T15:28:00025 March 2010 15:28:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat High Pressure Safety Injection Inoperable Due to Voids Identified in Suction Piping ENS 457242010-02-24T17:40:00024 February 2010 17:40:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Auxiliary Feedwater Pumps May Experience Runout at Low Steam Pressures ENS 442282008-05-21T00:56:00021 May 2008 00:56:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Decay Heat Removal Cooling Interupted During Core Reload ENS 438862008-01-08T17:42:0008 January 2008 17:42:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Potential Loca Injection Flow Rate Issue ENS 431572007-02-08T19:42:0008 February 2007 19:42:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Raw Water Pumps Declared Inoperable Due to a Potential Failure of the Pump Breaker Linkages ENS 430132006-11-27T19:30:00027 November 2006 19:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Momentary Loss of Shutdown Cooling Due to Rhr Isolation Signal ENS 426922006-07-07T22:00:0007 July 2006 22:00:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Auxiliary Feedwater Pump Recirculation Valve Inoperable 2016-03-18T16:28:00 | |
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