ENS 49774
ENS Event | |
|---|---|
16:15 Jan 29, 2014 | |
| Title | Secondary Containment Boundary Was Temporarily Blocked Open |
| Event Description | Title: Door Opened Under Administrative Control Could Have Prevented Fulfillment of Safety Functions to Control the Release of Radioactive Material and Mitigate the Consequences of an Accident
On January 29, 2014, it was determined a door credited as a Secondary Containment Boundary was temporarily blocked opened multiple times since January 25, 2014 under administrative control. Technical Specification 3.6.6.2 'Secondary Containment' is applicable and requires the system to be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In each instance where the door was blocked open, the requirements of Technical Specification 3.6.6.2 were entered and complied with. NUREG 1022 Revision 3 states inoperability of a single train system is reportable even though the plant's Technical Specifications may allow the condition to exist for a limited time. Although the plant was operated within the licensing basis, since Secondary Containment was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to control the release of radioactive material and mitigate the consequences of an accident. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D). The NRC Senior Resident Inspector has been notified.
The licensee is retracting this report based on the following: The purpose of this call is to retract the report made on January 29, 2014, Event Number 49774. Event Report number 49774 describes a condition in which the Millstone Power Station Unit 3 (MPS3) Secondary Containment was voluntarily rendered inoperable under administrative control. Using the criteria of NUREG-1022 Rev. 3, this condition report is not related to inoperability being due to one or more personnel errors, including procedure violations; equipment failures; inadequate maintenance; or design, analysis, fabrication, equipment qualification, construction, or procedural deficiencies and was declared inoperable as part of a planned evolution for maintenance or surveillance testing and done in accordance with an approved procedure and the plant's technical specifications. Therefore, this condition is not reportable and NRC Event 49774 is being retracted. The basis for this conclusion will be provided to the NRC Resident Inspector. The licensee informed the NRC Resident Inspector. Notified R1DO (Ferdas). |
| Where | |
|---|---|
Millstone  Connecticut (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+-1.28 h-0.0533 days <br />-0.00762 weeks <br />-0.00175 months <br />) | |
| Opened: | Adam Mcguire 14:58 Jan 29, 2014 |
| NRC Officer: | Charles Teal |
| Last Updated: | Mar 13, 2014 |
| 49774 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |