ENS 50097
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ENS Event | |
|---|---|
12:32 May 4, 2014 | |
| Title | Manual Initiation of the Reactor Protection System While Shutdown |
| Event Description | On 5/4/14 while the plant was in Mode 3 and the reactor not critical, unexpected position indications were observed on a Control Rod while withdrawing an Axial Power Shaping Rod (APSR). Due to the uncertainty of rod positions, the APSR was inserted into the core. The reactor trip breakers were then opened from the Control Room using the manual trip pushbuttons. All Control and Safety Rods were unlatched and fully inserted into the reactor core before the reactor trip breakers were opened.
This manual initiation of the Reactor Protection System with the reactor not critical is being reported per 10 CFR 50.72(b)(3)(iv)(A). The reportability of this event was determined based on an extent of condition review for Event Number 50086 that occurred 5/5/14. The failure to meet the 8-hour reporting requirement has been entered into the Corrective Action Program. The licensee notified the NRC Resident Inspector, the State of Ohio, and Ottawa and Lucas Counties. |
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000346/LER-2014-001 |
| Time - Person (Reporting Time:+101.23 h4.218 days <br />0.603 weeks <br />0.139 months <br />) | |
| Opened: | Robert W. Oesterle 17:46 May 8, 2014 |
| NRC Officer: | Dong Park |
| Last Updated: | May 8, 2014 |
| 50097 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 522322016-09-10T07:43:00010 September 2016 07:43:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Unit Trip Due to Main Generator Lock-Out ENS 517022016-01-30T06:23:00030 January 2016 06:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unanticipated Sfrcs Actuation While Restoring Main Feedwater to Steam Generators ENS 516962016-01-29T18:22:00029 January 2016 18:22:00 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 Protection System Actuation ENS 510612015-05-09T22:55:0009 May 2015 22:55:00 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 Unusual Event Declared Due to Steam Leak in the Turbine Building ENS 500862014-05-05T18:56:0005 May 2014 18:56:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram with Rod Motion While Shutdown ENS 500972014-05-04T12:32:0004 May 2014 12:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of the Reactor Protection System While Shutdown ENS 413302005-01-13T14:49:00013 January 2005 14:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Entry Into Technical Specification Required Shut Down Due to Loss of Essential Bus ENS 402082003-10-01T01:34:0001 October 2003 01:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Specified System Actuation ENS 401612003-09-16T04:30:00016 September 2003 04:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Coolant System Pressure Increase Caused a Valid Signal 2016-09-10T07:43:00 | |
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