ENS 44239
ENS Event | |
|---|---|
13:38 May 24, 2008 | |
| Title | Steam Generator Level Excursion |
| Event Description | On 5/24/2008 at 0938, with Beaver Valley Power Station Unit 2 (BVPS U2) in Mode 1 at 15% power during preparations for turbine startup, the unit experienced a steam generator level excursion. Attempts to manually control steam generator water level were unsuccessful.
Steam Generator narrow range levels exceeded the setpoint for P-14, Steam Generator Level High High Turbine Trip. The actuation of P-14 automatically actuated the following: trip of the running Main Feedwater pump, closure of the Main and Bypass Feedwater regulating valves, and closure of the Feedwater Containment isolation valves. In addition to these signals, a turbine trip signal is generated but the turbine was not yet on-line. The feedwater isolation signal has been reset and normal feedwater flow has been established. Preliminary investigation has revealed that a broken air line caused the 'A' Main Feedwater pump recirculation flow control valve to fail open. This initiated the steam generator level transient. Additional investigation is in progress. The trip of the Main Feedwater pumps automatically started both Motor Driven Auxiliary Feedwater pumps (MDAFW). The automatic start of the MDAFW pumps from this valid system actuation is reportable under 10CFR50.72(b)(3)(iv)(A). The plant is currently stable in Mode 1 at 15% reactor power." AFW injected into the core. 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: | 05000412/LER-2008-001 |
| Time - Person (Reporting Time:+1.47 h0.0613 days <br />0.00875 weeks <br />0.00201 months <br />) | |
| Opened: | Michael Mouser 15:06 May 24, 2008 |
| NRC Officer: | Joe O'Hara |
| Last Updated: | May 28, 2008 |
| 44239 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (15 %) |
| After | Power Operation (15 %) |
WEEKMONTHYEARENS 565272023-05-19T12:52:00019 May 2023 12:52:00
[Table view]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. 2023-05-19T12:52:00 | |