ENS 44899
ENS Event | |
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16:10 Jan 20, 2009 | |
Title | Invalid Actuation of Secondary Containment |
Event Description | Monticello Nuclear Generating Plant is making a telephone Report in Accordance with 10 CFR 50.73(a)(2)(iv)(A) Invalid Actuation of the Standby Gas Treatment and Secondary Containment Isolation Systems due to high resistance resulting from inadequate contact wipe of a relay. This report is being made in lieu of a written Licensee Event Report.
SPECIFIC TRAINS AND SYSTEMS THAT WERE ACTUATED The 'A' Standby Gas Treatment system actuated and Secondary Containment isolated. DESCRIPTION OF WHETHER EACH TRAIN ACTUATION WAS COMPLETE OR PARTIAL On January 20, 2009, during performance of Step 29 of Procedure 0003, Drywell High Pressure Scram and Groups 2, 3, & Secondary Containment Isolation Test and Calibration, the Standby Gas System automatically initiated and Secondary Containment isolated due to high contact resistance on a Drywell High Pressure HFA relay. This resulted in increased steam chase temperatures, entry into Action Statement TS 3.3.6.2.A for Secondary Containment Isolation Instrumentation, entry into Action Statement TS 3.6.4.1.A for Secondary Containment, entry into Action Statement TS 3.6.4.3.A for Standby Gas Treatment, and 10CFR50.73 reportability. DESCRIPTION OF WHETHER OR NOT THE SYSTEM STARTED AND FUNCTIONED SUCCESSFULLY All systems started and functioned successfully. The cause of the initiation of SBGT and isolation of Secondary Containment during performance of Step 29 of Procedure 0003 was the presence of high resistance at relay 16A-K60A, contacts 5-6. The cause of high resistance at relay 16A-K60A, contacts 5-6, was inadequate contact wipe. The cause of the inadequate contact wipe was inadequate contact wipe adjustment after replacement of HFA coils with the new Century series coil. The NRC Resident Inspector was notified of this event report. |
Where | |
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Monticello Minnesota (NRC Region 3) | |
Reporting | |
10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
Time - Person (Reporting Time:+1220.18 h50.841 days <br />7.263 weeks <br />1.671 months <br />) | |
Opened: | Ellis Pfeffer 11:21 Mar 12, 2009 |
NRC Officer: | Pete Snyder |
Last Updated: | Mar 12, 2009 |
44899 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 565842023-04-28T09:02:00028 April 2023 09:02:00
[Table view]10 CFR 50.73(a)(1), Submit an LER 60 Day Notification for an Invalid Actuation of Primary Containment Isolation Logic ENS 557082021-11-29T17:28:00029 November 2021 17:28:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of Secondary Containment Relays ENS 524512016-10-24T23:45:00024 October 2016 23:45:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Optional Telephonic Notification of Invalid Specified System Actuation ENS 448992009-01-20T16:10:00020 January 2009 16:10:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of Secondary Containment ENS 442112008-04-03T11:25:0003 April 2008 11:25:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of a Sbgt During Annunciator Test ENS 427882006-08-19T23:49:00019 August 2006 23:49:00 10 CFR 50.73(a)(1), Submit an LER Radiation Monitor Electrical Spike Causes Secondary Containment Isolation ENS 427402006-07-30T22:30:00030 July 2006 22:30:00 10 CFR 50.73(a)(1), Submit an LER Secondary Containment Isolation Due to 'B' Spent Fuel Rad Monitor Failure ENS 426522006-06-19T04:19:00019 June 2006 04:19:00 10 CFR 50.73(a)(1), Submit an LER Radiation Monitor Spiked Three Times 2023-04-28T09:02:00 | |