ENS 41179
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ENS Event | |
|---|---|
21:35 Nov 7, 2004 | |
| Title | "a" Auxiliary Feedwater (Afw) Pump Manually Started Due to Decreasing Steam Generator Water Level. |
| Event Description | The 'A' motor driven AFW pump was manually started in response to lowering Steam Generator (SG) level. The plant was in Mode 1 with reactor power at approximately 7%, preparing for startup of the turbine generator. Steam Generator Feedwater flow to the Steam Generators was being supplied by the main feedwater system through the main feedwater regulating bypass valves operating in automatic control. The operating crew observed a lowering trend in 'C' Steam Generator level. Upon reaching the lower end of the procedurally established normal control band (time=1633), the operating crew took the following actions in accordance with plant procedures: (1) the associated feedwater regulating bypass valve was taken to manual control to attempt restoration of normal SG level, (2) the 'A' motor driven AFW pump was manually started (time= 1635) to supply AFW to the SG and (3) reactor power lowered to reduce steam demand. These actions resulted in the restoration of 'C' SG level to normal. Normal operating SG level is 57%. Lo Lo Steam Generator Level Trip occurs at 25%. The lowest SG level observed during the evolution was approximately 43%. The cause of the irregular Feedwater control is currently being investigated. The plant is currently at approximately 2.5% power with all Steam Generator levels at normal operating levels. No automatic ESF Actuations occurred. The NRC Senior Resident was informed. |
| Where | |
|---|---|
Harris  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000400/LER-2004-006 |
| Time - Person (Reporting Time:+-0.52 h-0.0217 days <br />-0.0031 weeks <br />-7.12296e-4 months <br />) | |
| Opened: | Jim Stanford 21:04 Nov 7, 2004 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Nov 7, 2004 |
| 41179 - NRC Website
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WEEKMONTHYEARENS 561902022-10-31T00:57:00031 October 2022 00:57:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Auxiliary Feedwater System Actuation ENS 561892022-10-30T10:53:00030 October 2022 10:53:00 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 System Actuation ENS 560752022-08-28T07:29:00028 August 2022 07:29:00 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 Auxiliary Feedwater System Actuation ENS 558682022-04-29T08:05:00029 April 2022 08:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Auxiliary Feedwater System Actuation ENS 533182018-04-07T08:51:0007 April 2018 08:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System (Afw) ENS 523352016-10-26T15:42:00026 October 2016 15:42:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Containment Sump Suction Valve Opened During Containment Spray Pump Testing ENS 522912016-10-08T17:28:0008 October 2016 17:28:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Unusual Event Declared Due to Loss of Offsite Power ENS 522892016-10-08T05:50:0008 October 2016 05:50:00 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 Unplanned Reactor Trip and Safety Injection Due to Turbine Control Valve Transient ENS 497422014-01-18T15:16:00018 January 2014 15:16:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Alert Declared Due to Fire in 480V Bus ENS 463962010-11-05T05:04:0005 November 2010 05:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of an Emergency Diesel Generator Following Inadvertent De-Energization of Safety Bus ENS 444232008-08-19T13:05:00019 August 2008 13:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rod Control System Malfunctioned ENS 436762007-09-29T02:32:00029 September 2007 02:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of a Startup Transformer ENS 428482006-09-19T14:00:00019 September 2006 14:00:00 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 Lockout Signal ENS 416542005-05-01T04:21:0001 May 2005 04:21:00 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 Condensate Pump ENS 411792004-11-07T21:35:0007 November 2004 21:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation "a" Auxiliary Feedwater (Afw) Pump Manually Started Due to Decreasing Steam Generator Water Level. ENS 411292004-10-18T11:41:00018 October 2004 11:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Start ENS 407302004-05-06T16:52:0006 May 2004 16:52:00 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 Actuation of Auxiliary Feedwater System ENS 400842003-08-17T19:51:00017 August 2003 19:51:00 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 "a" Condensate Pump. 2022-08-28T07:29:00 | |
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