ENS 52618: Difference between revisions

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| event date = 03/09/2017 01:20 EST
| event date = 03/09/2017 01:20 EST
| last update date = 03/17/2017
| last update date = 03/17/2017
| title = Containment Airlock Function Lost Due To Equalizing Valve Not Closing
| title = Containment Airlock Function Lost Due to Equalizing Valve Not Closing
| event text = On March 9, 2017 at 0120 EST, the equalizing valve for the Watts Bar Nuclear Plant (WBN) Unit 2 upper containment airlock inboard door was found not closed while the outboard airlock door was open.  This created a containment bypass with leakage potentially greater than allowed by the design.  The operator immediately identified, after opening the outer door of the elevation 757 Air Lock, the pressure equalizing valve for the inner door was not fully closed. The outer door was promptly shut to isolate the airlock.  The inner door was then cycled which closed the equalizing valve.  The total time that a containment bypass was present is estimated at five minutes.
| event text = On March 9, 2017 at 0120 EST, the equalizing valve for the Watts Bar Nuclear Plant (WBN) Unit 2 upper containment airlock inboard door was found not closed while the outboard airlock door was open.  This created a containment bypass with leakage potentially greater than allowed by the design.  The operator immediately identified, after opening the outer door of the elevation 757 Air Lock, the pressure equalizing valve for the inner door was not fully closed. The outer door was promptly shut to isolate the airlock.  The inner door was then cycled which closed the equalizing valve.  The total time that a containment bypass was present is estimated at five minutes.
This condition was initially recognized as being potentially reportable.  However, the assessment performed at the time, based on operator control of the outer airlock door, concluded there was a reasonable assurance of meeting the safety function.  A subsequent independent review of this condition identified that this should have been reported under 10 CFR 50.72(b)(3)(v)(C) within eight hours of the event.
This condition was initially recognized as being potentially reportable.  However, the assessment performed at the time, based on operator control of the outer airlock door, concluded there was a reasonable assurance of meeting the safety function.  A subsequent independent review of this condition identified that this should have been reported under 10 CFR 50.72(b)(3)(v)(C) within eight hours of the event.

Latest revision as of 20:43, 1 March 2018

ENS 52618 +/-
Where
Watts Bar Tennessee Valley Authority icon.png
Tennessee (NRC Region 2)
Reporting
10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material
Time - Person (Reporting Time:+203.8 h8.492 days <br />1.213 weeks <br />0.279 months <br />)
Opened: Brian Mcilnay
17:08 Mar 17, 2017
NRC Officer: Mark Abramovitz
Last Updated: Mar 17, 2017
52618 - NRC Website
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