ENS 48047: Difference between revisions
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StriderTol (talk | contribs) (Created page by program invented by Mark Hawes) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
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| event date = 06/25/2012 13:30 EDT | | event date = 06/25/2012 13:30 EDT | ||
| last update date = 06/25/2012 | | last update date = 06/25/2012 | ||
| title = Reactor Feed Pump Trip Results | | title = Reactor Feed Pump Trip Results in Manual Reactor Scram | ||
| event text = At 1330 EDT on June 25, 2012, while restoring the Main Turbine Generator (MTG) to service after repairs to Main Unit Transformer 2B (MUT2B), Main Control Room (MCR) staff manually initiated a reactor scram in response to trip of both Reactor Feed Pumps (RFP). All control rods fully inserted. The lowest Reactor Water Level (RWL) reached was 154 inches and, as expected, HPCI and RCIC did not actuate. RWL was restored to normal using the Standby Feedwater (SBFW) system. RWL is currently being maintained in the normal level band with SBFW and Control Rod Drive (CRD) systems. No Safety Relief Valves (SRV) actuated. All isolations and actuations for RWL 3 occurred as expected. Investigation into the trip of RFPs continues. | | event text = At 1330 EDT on June 25, 2012, while restoring the Main Turbine Generator (MTG) to service after repairs to Main Unit Transformer 2B (MUT2B), Main Control Room (MCR) staff manually initiated a reactor scram in response to trip of both Reactor Feed Pumps (RFP). All control rods fully inserted. The lowest Reactor Water Level (RWL) reached was 154 inches and, as expected, HPCI and RCIC did not actuate. RWL was restored to normal using the Standby Feedwater (SBFW) system. RWL is currently being maintained in the normal level band with SBFW and Control Rod Drive (CRD) systems. No Safety Relief Valves (SRV) actuated. All isolations and actuations for RWL 3 occurred as expected. Investigation into the trip of RFPs continues. | ||
At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDG) were operable and no safety related equipment was out of service. This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an event that results in actuation of the reactor protection system (RPS) when the reactor is critical. | At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDG) were operable and no safety related equipment was out of service. This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an event that results in actuation of the reactor protection system (RPS) when the reactor is critical. | ||
Latest revision as of 22:03, 1 March 2018
| Where | |
|---|---|
Fermi  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000341/LER-2012-003 |
| Time - Person (Reporting Time:+-0.87 h-0.0363 days <br />-0.00518 weeks <br />-0.00119 months <br />) | |
| Opened: | Jeff Groff 16:38 Jun 25, 2012 |
| NRC Officer: | Dong Park |
| Last Updated: | Jun 25, 2012 |
| 48047 - NRC Website
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