ENS 54369
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
10:35 Nov 4, 2019 | |
| Title | Manual Reactor Trip Due to Steam Dump Transient |
| Event Description | At 0535 [EST] on November 4, 2019, with Unit 1 in mode 1 at 15 [percent] power, the reactor was manually tripped due to the lifting of an 'A' Main Steamline Safety Valve following a Condenser Steam Dump transient. The trip response was not complex, with all systems responding normally post-trip, and all control rods fully inserted into the core.
Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the Main Condenser by using the Condenser Steam Dump Valves. Offsite power is available and is currently supplying Normal and Emergency busses. The plant is currently stable in mode 3. Unit 2 is unaffected by this event and remains at 100 [percent] power in mode 1. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
| Beaver Valley Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000334/LER-2019-002 Manual Reactor Trip at 15% Power Due to Lifting of the 1A Main Steam Safety Valve |
| Time - Person (Reporting Time:+-1.48 h-0.0617 days <br />-0.00881 weeks <br />-0.00203 months <br />) | |
| Opened: | Mark Benkowski 09:06 Nov 4, 2019 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Nov 4, 2019 |
| 54369 - 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 54369\u003C/a\u003E - \u003Ca href=\"/Beaver_Valley\" title=\"Beaver Valley\"\u003EBeaver Valley\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EManual Reactor Trip Due to Steam Dump Transient\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 54369 - Beaver Valley\n","link":"","lat":40.62256111111111,"lon":-80.43140277777778,"icon":""}],"imageoverlays":null} | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (15 %) |
| After | Hot Standby (0 %) |
Beaver Valley with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | |
WEEKMONTHYEARENS 571322024-05-19T04:30:00019 May 2024 04:30:00
[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 ENS 570752024-04-13T04:35:00013 April 2024 04:35:00 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 559432022-06-15T11:24:00015 June 2022 11:24:00 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 Auxiliary Feedwater Actuation ENS 555862021-11-17T18:13:00017 November 2021 18:13:00 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 Auxiliary Feedwater Actuation ENS 555722021-11-12T15:07:00012 November 2021 15:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Increasing Steam Generator Water Levels ENS 555072021-10-05T10:32:0005 October 2021 10:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Auxiliary Feedwater Actuation ENS 543692019-11-04T10:35:0004 November 2019 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Steam Dump Transient ENS 530562017-11-07T10:04:0007 November 2017 10:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip Due to Main Unit Generator Over Current ENS 501242014-05-20T12:35:00020 May 2014 12:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Reactor Startup ENS 496972014-01-06T21:59:0006 January 2014 21:59:00 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 Transformer Fault ENS 495052013-11-05T23:28:0005 November 2013 23:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Notification of Unusual Event Due to Explosion and Fire in the Turbine Building ENS 467442011-04-10T07:45:00010 April 2011 07:45:00 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip While Performing a Technical Specification Required Shutdown ENS 428342006-09-08T01:57:0008 September 2006 01:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Spurious Opening of a Reactor Trip Breaker ENS 424672006-04-02T18:02:0002 April 2006 18:02:00 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 a Main Generator Trip ENS 403202003-11-13T16:35:00013 November 2003 16:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from 100% Power with Cause Being Investigated ENS 402472003-10-15T03:55:00015 October 2003 03:55:00 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 "B" Steam Generator Water Level. 2024-05-19T04:30:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_54369&oldid=2508129"