ENS 42428
ENS Event | |
|---|---|
16:20 Feb 10, 2006 | |
| Title | Invalid Specified System Actuations |
| Event Description | The following information is provided as a 60 day telephone notification to NRC under 10 CFR 50.73(a)(1) in lieu of submitting a written LER to report a condition that resulted in an invalid actuation of a 10 CFR 50.73(a)(2)(iv)(B) system. NUREG1022 Revision 2 identifies the information that needs to be reported as discussed below.
(a) The specific train(s) and system(s) that were actuated: On February 10, 2006, at 1120 EST, a surveillance was in progress to calibrate the Division 2 Fuel Pool Ventilation Exhaust Radiation Monitor D11-K611D. During jumper removal an adjacent terminal was contacted by the jumper while still connected to a 24 VDC power source resulting in a blown power supply fuse. The loss of the power supply resulted in the following automatic actions: Primary Containment Isolation Valve Group 14; Drywell and Suppression Chamber Ventilation System; and Group 16, Nitrogen Inerting System received an isolation signal. All primary containment isolation valves in both groups were previously in their safety function position (closed). Secondary containment isolated resulting in a trip of the Reactor Building Heating and Ventilation System and Division 2 Standby Gas Treatment System automatically started. The Control Center Heating, Ventilating and Air Conditioning System automatically shifted into the Recirculation mode. The initiation signal was invalid because it did not result in response to an actual high radiation condition, nor did it trip as a result of any other requirement for initiation of the safety function, such as a downscale or inoperable trip, for example. (b) Whether each train actuation was complete or partial. The Division 2 Standby Gas Treatment System automatically started, secondary containment fully isolated, Reactor Building Heating and Ventilation System tripped, and the Control Center Heating, Ventilating and Air Conditioning System automatically shifted into the Recirculation mode. These were complete actuations. The primary containment isolation valves Group 14 and 16 remained in their safety function (closed) position. This was a complete actuation. (c) Whether or not the system started and functioned successfully. The above systems functioned successfully. The licensee will notify the NRC Resident Inspector. |
| Where | |
|---|---|
Fermi  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+838.23 h34.926 days <br />4.989 weeks <br />1.148 months <br />) | |
| Opened: | Dave Coseo 14:34 Mar 17, 2006 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Mar 17, 2006 |
| 42428 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 528592017-03-24T19:48:00024 March 2017 19:48:00
[Table view]10 CFR 50.73(a)(1), Submit an LER Invalid Specified System Actuation During Testing ENS 511282015-05-24T23:30:00024 May 2015 23:30:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Optional Telephonic Notification for an Invalid Actuation of Containment Isolation Valves ENS 501122014-03-19T00:30:00019 March 2014 00:30:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Optional Telephonic Notification for an Invalid Actuation of Containment Isolation Valves ENS 438502007-10-22T23:30:00022 October 2007 23:30:00 10 CFR 50.73(a)(1), Submit an LER Invalid System Actuation ENS 438402007-10-14T07:00:00014 October 2007 07:00:00 10 CFR 50.73(a)(1), Submit an LER Inadvertent Actuation of Emergency Diesel Generator ENS 424282006-02-10T16:20:00010 February 2006 16:20:00 10 CFR 50.73(a)(1), Submit an LER Invalid Specified System Actuations ENS 408992004-05-30T14:40:00030 May 2004 14:40:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of Containment Isolation Valves Due to Partial Loss of 120 Vac Modular Power Unit 2 Loads 2017-03-24T19:48:00 | |