ENS 49800: Difference between revisions
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| event date = 12/11/2013 08:18 EST | | event date = 12/11/2013 08:18 EST | ||
| last update date = 02/06/2014 | | last update date = 02/06/2014 | ||
| title = Invalid Actuation | | title = Invalid Actuation of Primary Containment Isolation System (Pcis) Valves During I&C Maintenance | ||
| event text = This 60-day report, as allowed by 10 CFR 50.73(a)(1 ), is being made per 10 CFR 50.73(a)(2)(iv)(A) to describe an unplanned, invalid closure of Unit 2 Primary Containment Isolation System (PCIS) valves. | | event text = This 60-day report, as allowed by 10 CFR 50.73(a)(1 ), is being made per 10 CFR 50.73(a)(2)(iv)(A) to describe an unplanned, invalid closure of Unit 2 Primary Containment Isolation System (PCIS) valves. | ||
On December 11, 2013, at 0818 EST, an instrument technician was adjusting the output voltage of the 'A' 120-volt Reactor Protection System (RPS) motor-generator (MG) set, which is the normal power supply for the 'A' RPS bus. As the adjustment potentiometer was being moved, output voltage momentarily dropped below the setpoint of an Electrical Protection Assembly (EPA) on the 'A' RPS bus. The EPA tripped and removed power from the 'A' RPS bus. Removing power from the RPS bus resulted in PCIS valves receiving a close signal. Affected valves or systems were a Reactor Water Sample valve, Main Steam Line Drain valves, Containment Atmospheric Control System valves, Drywell Equipment Drain and Floor Drain valves, and a Reactor Water Cleanup System valve. | On December 11, 2013, at 0818 EST, an instrument technician was adjusting the output voltage of the 'A' 120-volt Reactor Protection System (RPS) motor-generator (MG) set, which is the normal power supply for the 'A' RPS bus. As the adjustment potentiometer was being moved, output voltage momentarily dropped below the setpoint of an Electrical Protection Assembly (EPA) on the 'A' RPS bus. The EPA tripped and removed power from the 'A' RPS bus. Removing power from the RPS bus resulted in PCIS valves receiving a close signal. Affected valves or systems were a Reactor Water Sample valve, Main Steam Line Drain valves, Containment Atmospheric Control System valves, Drywell Equipment Drain and Floor Drain valves, and a Reactor Water Cleanup System valve. | ||
Latest revision as of 21:51, 1 March 2018
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+1365.7 h56.904 days <br />8.129 weeks <br />1.871 months <br />) | |
| Opened: | Stephen W. Reed 11:00 Feb 6, 2014 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Feb 6, 2014 |
| 49800 - NRC Website
| |