ENS 50097: Difference between revisions
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| event date = 05/04/2014 08:32 EDT | | event date = 05/04/2014 08:32 EDT | ||
| last update date = 05/08/2014 | | last update date = 05/08/2014 | ||
| title = Manual Initiation | | title = Manual Initiation of the Reactor Protection System While Shutdown | ||
| event text = 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. | | event text = 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. | 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. | ||
Latest revision as of 20:50, 1 March 2018
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000346/LER-2014-001 Regarding Manual Initiation of the Reactor Protection System Due to Unexpected Indication of Control Rod Movement |
| 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
| |