ENS 57215: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 24: | Line 24: | ||
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: | The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: | ||
The cause of the main feedwater pump 'A' miniflow valve failing open was unknown and under investigation at the time of the notification of this event to the NRC. | The cause of the main feedwater pump 'A' miniflow valve failing open was unknown and under investigation at the time of the notification of this event to the NRC. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/ | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240711en.html#en57215 | ||
}}{{unit info | }}{{unit info | ||
| Unit = 3 | | Unit = 3 | ||
Latest revision as of 06:20, 11 July 2024
ENS Event | |
|---|---|
01:25 Jul 9, 2024 | |
| Title | Manual Reactor Trip and Automatic Safeguards Actuation |
| Event Description | The following information was provided by the licensee via email:
At 2125 EDT on 07/08/2024, with Unit 3 in Mode 1 at 100 percent power, the reactor was manually tripped due to main feedwater pump `A' miniflow valve failing open, which resulted in lowering steam generator water level. Additionally, an automatic safeguards actuation occurred due to the cooldown of the reactor coolant system. The trip was not complex, with all safety systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by the passive residual heat removal heat exchanger. Units 1, 2, and 4 are not affected. Due to the core makeup tank actuation, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(A). The reactor protection system actuation while critical is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, this event is reportable per 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid containment isolation actuation and a valid passive residual heat removal heat exchanger actuation. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The cause of the main feedwater pump 'A' miniflow valve failing open was unknown and under investigation at the time of the notification of this event to the NRC. |
| Where | |
|---|---|
Vogtle  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />) | |
| Opened: | Tommie Sweat 01:11 Jul 9, 2024 |
| NRC Officer: | Ernest West |
| Last Updated: | Jul 9, 2024 |
| 57215 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 57215\u003C/a\u003E - \u003Ca href=\"/Vogtle\" title=\"Vogtle\"\u003EVogtle\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EManual Reactor Trip and Automatic Safeguards Actuation\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 57215 - Vogtle\n","link":"","lat":33.13062222222222,"lon":-81.77135277777778,"icon":"/w/images/1/14/Southern_Nuclear_icon.png"}],"imageoverlays":null} | |
Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Safe Shutdown (0 %) |
Vogtle 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)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 577342025-05-28T16:53:00028 May 2025 16:53:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Auxiliary Feedwater Actuation ENS 573262024-09-17T05:27:00017 September 2024 05:27:00 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)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip and Manual Safeguards Actuation ENS 572152024-07-09T01:25:0009 July 2024 01:25:00 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)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Trip and Automatic Safeguards Actuation ENS 571872024-06-22T11:28:00022 June 2024 11:28:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Reactor Protection System (Rps) ENS 571642024-06-05T20:48:0005 June 2024 20:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 566922023-08-22T21:24:00022 August 2023 21:24:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Actuation of Auxiliary Feedwater System ENS 566322023-07-21T15:48:00021 July 2023 15:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 566142023-07-09T17:28:0009 July 2023 17:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 564972023-05-02T08:23:0002 May 2023 08:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip ENS 564602023-04-10T04:48:00010 April 2023 04:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 564142023-03-16T01:57:00016 March 2023 01:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 563112023-01-14T12:21:00014 January 2023 12:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Reactor Protection System (RPS) ENS 562942023-01-04T03:59:0004 January 2023 03:59:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power Source ENS 561472022-10-06T06:44:0006 October 2022 06:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Reactor Protection System (RPS) ENS 558752022-05-03T19:41:0003 May 2022 19:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Actuation of Auxiliary Feedwater System ENS 549952020-11-12T22:32:00012 November 2020 22:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Turbine Trip ENS 545962020-03-21T20:44:00021 March 2020 20:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the 1B Emergency Diesel Generator ENS 543182019-10-09T14:23:0009 October 2019 14:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Emergency Diesel Generator and Auxilliary Feedwater System ENS 541752019-07-19T13:45:00019 July 2019 13:45:00 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 Main Steam Isolation Valve Failing Shut ENS 539672019-03-31T01:30:00031 March 2019 01:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Msiv Failing Closed ENS 536432018-10-04T04:00:0004 October 2018 04:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation En Revision Imported Date 10/22/2018 ENS 534842018-07-03T04:00:0003 July 2018 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to High Steam Generator Water Level ENS 529922017-09-26T09:43:00026 September 2017 09:43:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of the 2B Emergency Diesel Due to a Valid Undervoltage Signal ENS 526192017-03-17T19:17:00017 March 2017 19:17:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Emergency Diesel Generator ENS 525342017-02-03T20:45:0003 February 2017 20:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manual Reactor Trip Due to Loop 1 Msiv Starting to Fail Closed ENS 519562016-05-25T06:06:00025 May 2016 06:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Lowering Steam Generator Water Level ENS 508942015-03-14T16:07:00014 March 2015 16:07:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Actuation During Surveillance Test ENS 508932015-03-14T08:29:00014 March 2015 08:29:00 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)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip on System Injection Actuation Signal ENS 505262014-10-12T13:44:00012 October 2014 13:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Reactor Startup ENS 503142014-07-27T18:09:00027 July 2014 18:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Main Feed Pump During Testing ENS 500312014-04-13T00:08:00013 April 2014 00:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Main Steam Isolation Valve Failing Shut ENS 500062014-04-08T08:28:0008 April 2014 08:28:00 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 Low Steam Generator Level ENS 494612013-10-22T15:44:00022 October 2013 15:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Decreasing Condenser Vacuum ENS 494532013-10-19T10:43:00019 October 2013 10:43:00 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 487882013-02-27T04:02:00027 February 2013 04:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Excessive Reactor Coolant Pump Seal Leakoff Flow ENS 483852012-10-05T09:14:0005 October 2012 09:14:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Auxiliary Feedwater Actuation ENS 478362012-04-14T17:46:00014 April 2012 17:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Low Main Feedwater Flow ENS 472242011-08-31T13:06:00031 August 2011 13:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip on Hi-Hi Steam Generator Level Results in Automatic Reactor Trip ENS 467722011-04-20T21:34:00020 April 2011 21:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 455882009-12-23T20:25:00023 December 2009 20:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Rps Actuation Due to Loss of Instrument Air ENS 455572009-12-10T04:10:00010 December 2009 04:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Following High Turbine Vibration ENS 455472009-12-07T23:01:0007 December 2009 23:01:00 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 a Turbine Trip Caused by Low Condenser Vacuum ENS 433132007-04-23T14:24:00023 April 2007 14:24:00 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 Generator Ground Relay Actuation ENS 429422006-10-28T16:23:00028 October 2006 16:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 428062006-08-27T10:31:00027 August 2006 10:31:00 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 Reactor Coolant Pump Trip ENS 425062006-04-17T04:26:00017 April 2006 04:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped Due to Failure of a Main Feed Regulating Valve to Control Steam Generator Level ENS 420582005-10-17T22:16:00017 October 2005 22:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Low Steam Generator Level ENS 416532005-04-30T01:55:00030 April 2005 01:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip - Lowering Steam Generator Level on Loop #1 ENS 413232005-01-11T12:19:00011 January 2005 12:19:00 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 Main Turbine Trip ENS 412132004-11-20T16:40:00020 November 2004 16:40:00 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)(iv)(A), System Actuation - ECCS Discharge Unexpected Automatic Reactor Trip During Surveillance Testing with Si Injection ENS 406822004-04-18T16:38:00018 April 2004 16:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater System Actuation Due to Main Feed Pump Trips ENS 406152004-03-28T03:05:00028 March 2004 03:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Feedwater Pump Speed Control ENS 402682003-10-22T05:03:00022 October 2003 05:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation High Pressure Hose Connection Failed Resulting in a Train "a" Manual Steam Line Isolation 2025-05-28T16:53:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_57215&oldid=3651408"