ENS 45828
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ENS Event | |
|---|---|
21:22 Apr 8, 2010 | |
| Title | Technical Specification Required Shutdown Due to Inoperable Steam Generator Inlet Isolation Valve |
| Event Description | At 1622 hours0.0188 days <br />0.451 hours <br />0.00268 weeks <br />6.17171e-4 months <br /> CDT, an electrical ground on 480 Volt Bus 1B3A was determined to be from a supply cable to Motor Control Center (MCC)-3A1. Isolating loads on this MCC required securing power to HCV-1385, Steam Generator RC-2B Inlet Isolation Valve. This condition results in the valve being unable to close on a Steam Generator Isolation Signal (SGIS), which requires entry into Technical Specification 2.0.1(1). This Technical Specification requires the plant to be placed in a Hot Shutdown condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. A plant shutdown to Mode 3 was commenced at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> CDT.
The licensee notified the NRC Resident Inspector.
At 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br /> CDT, the Reactor was manually tripped from 22% Reactor Power in order to meet the requirements of Technical Specification 2.0.1(1) and have the reactor in a hot shutdown condition. All systems functioned properly. At 2124 CDT, the plant entered Mode 3 Shutdown Condition. AT 2235 CDT, HCV-1385, Steam Generator RC-2B Inlet Isolation Valve has been manually closed. Technical Specification 2.0.1(1) has been exited. The licensee is reporting the manual scram under 10CFR50.72(b)(2)(iv)(B). The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Fort Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-0.8 h-0.0333 days <br />-0.00476 weeks <br />-0.0011 months <br />) | |
| Opened: | Nathan Seid 20:34 Apr 8, 2010 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Apr 9, 2010 |
| 45828 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (75 %) |
Fort Calhoun with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 522012016-08-25T20:23:00025 August 2016 20:23:00
[Table view]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 Unanalyzed Condition Involving Potential Tornado Missile Damage ENS 520332016-06-22T13:41:00022 June 2016 13:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip ENS 519172016-05-10T16:38:00010 May 2016 16:38:00 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 Containment Cooling Water System Inoperable Due to Unanalyzed Condition ENS 514872015-10-21T18:50:00021 October 2015 18:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Pressurizer Heater Bank Potential Circuit Failure Vulnerability ENS 508002015-02-09T23:30:0009 February 2015 23:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Safety Injection Tank Level Results in an Unanalyzed Condition ENS 506882014-12-17T16:14:00017 December 2014 16:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of Load ENS 502142014-06-20T05:01:00020 June 2014 05:01:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 500382014-04-15T20:15:00015 April 2014 20:15:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Failure of Control Room Air Conditioning ENS 499262014-03-17T17:02:00017 March 2014 17:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip Initiated by Loss of Stator Cooling Water ENS 497172014-01-12T09:23:00012 January 2014 09:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Control Rod Position Deviation ENS 497042014-01-09T11:18:0009 January 2014 11:18:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Inoperable Raw Water Pumps. ENS 494782013-10-28T17:30:00028 October 2013 17:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Event Could Result in a Hot Short That Could Adversely Impact Safe Shutdown Equipment ENS 493782013-09-23T18:40:00023 September 2013 18:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Epoxy Floor Coatings Do Not Meet Design Basis Requirements in Two Rooms ENS 493242013-09-05T13:31:0005 September 2013 13:31:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Low Pressure Safety Injection Pump Run Out Condition ENS 491192013-06-14T16:00:00014 June 2013 16:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Invalid Conditions Discovered Due to Exclusion of Small Bore Piping from Analysis ENS 491122013-06-13T13:05:00013 June 2013 13:05:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 490502013-05-17T05:00:00017 May 2013 05:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Embedment Depth for Seismic Anchors Inadequate ENS 488062013-03-04T20:00:0004 March 2013 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Mechanical Seal Material Design ENS 487872013-02-27T02:12:00027 February 2013 02:12:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Relay Backing Plate Fasteners Discovered to Be at Less than Specified Torque ENS 487812013-02-24T23:00:00024 February 2013 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Inverters Potentially Inoperable During Emergency Diesel Generator Operation ENS 487302013-02-07T20:30:0007 February 2013 20:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Possible Run-Out of High Pressure Safety Injection Pump ENS 480942012-07-11T21:03:00011 July 2012 21:03:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Analysis of Internal Containment Support Beam Exceeds Load Combination Limit ENS 479922012-06-04T20:14:0004 June 2012 20:14:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Coolant System in a Degraded Condition Due to an Instrument Rack Seismic Design Issue ENS 479002012-05-04T15:00:0004 May 2012 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Containment Equipment Not Analyzed for Environmental Conditions of Record ENS 478922012-05-02T16:55:0002 May 2012 16:55:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Unanalyzed Condition with Containment Pressure Instruments ENS 478622012-04-25T14:00:00025 April 2012 14:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Conditions Resulting from a Non-Conservative Error in Calculations ENS 478842012-03-02T13:41:0002 March 2012 13:41:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Degradation of Reactor Containment Electrical Penetration Seals ENS 476582012-02-10T06:00:00010 February 2012 06:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Guidance Not Adequate to Mitigate a Design Basis Flood ENS 478482011-10-06T18:44:0006 October 2011 18:44:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Waste Disposal System Class One Seismic Support Inoperable ENS 470882011-07-22T13:30:00022 July 2011 13:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Supression Pumps Inoperable ENS 469652011-06-16T17:30:00016 June 2011 17:30:00 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 Additional Penetration Identified for Mitigation During Walkdown ENS 465062010-12-23T16:50:00023 December 2010 16:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Uncomplicated Reactor Trip from 100% Power ENS 463682010-10-27T17:22:00027 October 2010 17:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit Commenced Shutdown After Declaring Containment Spray Inoperable ENS 462972010-09-30T21:16:00030 September 2010 21:16:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Potential Flooding Via Condensate Drain Lines ENS 458282010-04-08T21:22:0008 April 2010 21:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Steam Generator Inlet Isolation Valve ENS 454672009-10-26T15:50:00026 October 2009 15:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Pressurizer and Feedwater Storage Tank Level Indications Do Not Meet Appendix R Requirements ENS 448512009-02-13T21:26:00013 February 2009 21:26:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unusual Event - Engineering Analysis Requires Technical Specification Shutdown ENS 440662008-03-15T13:33:00015 March 2008 13:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Turbine Trip ENS 429432006-10-28T22:09:00028 October 2006 22:09:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 429022006-10-12T22:30:00012 October 2006 22:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Steam Generator Instrumentation Nonconformance ENS 428962006-10-10T20:00:00010 October 2006 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Containment Spray Valve Mispositioned ENS 424862006-04-10T15:55:00010 April 2006 15:55:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Personnel Air Lock Door Equalizing Valve Leaking by ENS 414462005-02-27T03:34:00027 February 2005 03:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Plant Had a Reactor Trip from 16.1% Power Due to a Loss of Turbine Load Signal ENS 401562003-09-13T01:55:00013 September 2003 01:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Unanticipated Negative Axial Shape Index (Asi). 2016-08-25T20:23:00 | |
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