ENS 53317
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ENS Event | |
|---|---|
16:17 Apr 5, 2018 | |
| Title | Secondary Containment Hatch Left Open |
| Event Description | On Thursday, April 5, 2018, at approximately 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br /> Central Daylight Time, Entergy contract personnel opened the personnel hatch allowing access to the roof of the Secondary Containment Building for the purposes of performing an inspection of various items located on the roof.
During the time period the individuals were on the roof, the hatch was left open. An individual was adjacent to the door with a radio and had constant communication link with the control room operator. Pursuant 10 CFR 50.72(b)(3)(v)(C), and 10 CFR 50.72(b)(3)(v)(D) this event is being reported as an event or condition that could have prevented the fulfillment of a safety function. Because the site had an individual briefed and at the door in constant communications with the control room to close the hatch if condition required such an action, this event is not viewed as an actual loss of safety function. The NRC Resident Inspector was notified. |
| Where | |
|---|---|
Grand Gulf  Mississippi (NRC Region 4) | |
| 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:+2.1 h0.0875 days <br />0.0125 weeks <br />0.00288 months <br />) | |
| Opened: | Jay Comfort 18:23 Apr 5, 2018 |
| NRC Officer: | Steven Vitto |
| Last Updated: | Apr 5, 2018 |
| 53317 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Grand Gulf with 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
WEEKMONTHYEARENS 569382024-01-29T16:05:00029 January 2024 16:05:00
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Mitigate the Consequences of an Accident Both Divisions of Drywell Vacuum Relief Declared Inoperable ENS 528432017-07-10T02:58:00010 July 2017 02:58:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Safety Function - Control Room Envelope Inoperable ENS 525162017-01-28T00:08:00028 January 2017 00:08:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray Declared Inoperable ENS 514732015-10-14T17:20:00014 October 2015 17:20:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Two Containment Isolation Valves Not Properly Tested Per Technical Specifications ENS 514592015-10-08T00:30:0008 October 2015 00:30:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Rendered Inoperable ENS 507862015-02-04T15:34:0004 February 2015 15:34:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Ventilation Inoperable Due to Mispositioned Ventilation Inspection Port ENS 496472013-12-17T19:32:00017 December 2013 19:32:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Containment Isolation Capability Due to Surveillance Procedure Error ENS 466872011-03-20T03:36:00020 March 2011 03:36:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray Valve Breaker Overcurrent Trip Setpoint Out of Tolerance ENS 463342010-10-14T09:22:00014 October 2010 09:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Trains of Control Room Air Conditioning Inoperable ENS 453162009-08-31T15:14:00031 August 2009 15:14:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Boundary Door Inoperable ENS 416502005-04-29T06:27:00029 April 2005 06:27:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Core Isolation Cooling Full Flow Test Line May Not Isolate ENS 416452005-04-27T23:07:00027 April 2005 23:07:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Main Steam Line Drain Containment Isolation Valves May Not Isolate ENS 409522004-08-14T15:25:00014 August 2004 15:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Grand Gulf Standby Service Water "C" and High Pressure Core Spray Declared Inoperable 2024-01-29T16:05:00 | |
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