ENS 45000
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
05:15 Apr 20, 2009 | |
| Title | Auxiliary Feedwater Actuation on Valid Steam Generator Hi-Hi Signal During Shutdown |
| Event Description | On April 20,2009 at 0115 during Beaver Valley Power Station Unit 1 shutdown and cooldown in support of the 19th refueling outage, Unit 1 experienced an Engineered Safety Feature (ESF) actuation P-14 due to Steam Generator (SG) HI-HI water level in the 'B' Steam Generator. This ESF actuation initiated automatic actions resulting in full feedwater isolation, trip of the only operating 'B' main feed and the start of two Auxiliary Feedwater System pumps. The unplanned automatic initiation of the Auxiliary Feedwater system [was] due to the Main Feedwater pump trip. The P-14 automatic ESF features properly closed the main and bypass feedwater regulating valves and [caused the] closure of the Feedwater Containment Isolation valves. A turbine trip signal was generated but the turbine was not on-line. The automatic start of the MDAFW pumps from this valid signal is reportable under 10CFR50.72(b)(3)(iv)(A).
The cause of the steam generator high level transient is the failure of the FCV-1FW-489, 'B' steam generator feed water bypass level control to automatically maintain level. Attempts to control the level manually were not successful. Additional investigation is in progress. P-14 ESF actuation reset actions are being performed. Unit one cooldown continues using the MDAFW pumps and controls. AFW continues to be injected into the steam generators. The licensee notified the NRC resident Inspector. |
| Where | |
|---|---|
| Beaver Valley Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000334/LER-2009-002 Regarding Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown |
| Time - Person (Reporting Time:+-0.1 h-0.00417 days <br />-5.952381e-4 weeks <br />-1.3698e-4 months <br />) | |
| Opened: | George E. Storolis 05:09 Apr 20, 2009 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Apr 20, 2009 |
| 45000 - 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 45000\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\u003EAuxiliary Feedwater Actuation on Valid Steam Generator Hi-Hi Signal During Shutdown\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 45000 - Beaver Valley\n","link":"","lat":40.62256111111111,"lon":-80.43140277777778,"icon":""}],"imageoverlays":null} | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
Beaver Valley with 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 575352025-02-05T15:02:0005 February 2025 15:02:00
[Table view]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 571322024-05-19T04:30:00019 May 2024 04:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip 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 565272023-05-19T12:52:00019 May 2023 12:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System (AFW) 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 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 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 493922013-09-30T06:38:00030 September 2013 06:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Start of Motor Driven Auxiliary Feedwater Pump 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 450002009-04-20T05:15:00020 April 2009 05:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Actuation on Valid Steam Generator Hi-Hi Signal During Shutdown ENS 442392008-05-24T13:38:00024 May 2008 13:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Steam Generator Level Excursion 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. 2025-02-05T15:02:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_45000&oldid=425905"