ENS 41555
ENS Event | |
|---|---|
12:18 Feb 14, 2005 | |
| Title | Inadvertant Safety System Actuation During Maintenance |
| Event Description | The following information was provided by the licensee via fax (licensee text in quotes):
At 0718 on February 14, 2005, with the James A. FitzPatrick Nuclear Power Plant operating at 100% reactor power, the High Voltage Power Supply (HVPS) for Reactor Building (RB) Radiation Monitor 17RM-452A was inadvertently de-energized. At 0724 the HVPS was re-energized and the technician began to adjust the output of the high voltage power supply. This adjustment resulted in an unanticipated voltage spike in the radiation monitor circuit. The voltage spike caused the radiation monitor to see a false Hi-Hi signal resulting in an actuation of the RB ventilation system isolation logic, start-up of the 'A' Standby Gas Treatment (SBGT) System, and a Half PCIS Group II Isolation. AOP-15, Isolation Verification and Recovery, was entered and at 0728 an 'A' train Group II PCIS Isolation was verified for that Channel. At 0750 AOP-15 was exited and plant systems were restored from the Half Group II PCIS Isolation. The reactor remained at 100% power throughout the event, and short-term LCOs were entered for equipment isolated as a result of the isolation, as applicable. While the Hi-Hi signal was falsely generated by the voltage spike encountered when re-energizing the HVPS the actuation logic functioned properly and the plant equipment responded as designed. There were no equipment failures associated with this event and neither plant operation nor the health and safety of the public were affected by this event. The condition meets the reporting criteria of 10 CFR 50.73 (a)(2)(iv)(a) because the invalid RB Radiation Monitor Hi - Hi signal resulted in a general containment isolation signal affecting containment isolation valves in more than one system ('A' SBGT, 'A' H2/02 Exosensors, 'A' Drywell Cam, 'A' Containment Atmosphere Dilution (CAD), 'A' PCP Vent and Purge). Since the signal was invalid this event meets the criteria in 10 CFR 50.73 (a)(1) for being reported as a 60-day phone call rather than as an LER. The event has been entered into the corrective action program and the resident inspector has been briefed. The apparent cause evaluation identified 1) a failure on the part of the technicians to plan for or provide a barrier to prevent the inadvertent actuation of the HVPS switch resulting in the initial deenergization of the radiation monitor circuit and then 2) failure to recognize that the restoration of the HVPS switch after inadvertent actuation should have been accomplished by entering the site work process and obtaining a work order which would have allowed for proper review and incorporation of barriers to minimize the probability of inadvertent isolations. The licensee notified the NRC Resident Inspector and the State. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+1082.18 h45.091 days <br />6.442 weeks <br />1.482 months <br />) | |
| Opened: | Andy Halliday 14:29 Mar 31, 2005 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Mar 31, 2005 |
| 41555 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 526452017-01-31T19:25:00031 January 2017 19:25:00
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