ENS 49607
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
20:40 Dec 4, 2013 | |
| Title | a Potential Electrical Hot Short in the Rhr Shutdown Cooling Control Cable Could Result in an Inter-System Loca |
| Event Description | As a result of questions raised by inspectors as part of the 2013 Triennial Fire Protection Inspection, a vulnerability from a postulated fire in the Unit 1 Cable Spreading Room was identified. This vulnerability involved the assumption of a fire occurring in Fire Area 0024A (Cable Spreading Room) which would create an inter-cable vulnerability that could result in an inter-system LOCA [Loss of Coolant Accident]. Hatch's licensing basis included credit for the use of disconnect or remote shutdown panel 'Emergency' switches located on the respective remote shutdown panels to isolate the circuits in the cable spreading room thereby eliminating this vulnerability. However, the presence of these switches does not fully address this vulnerability. The Unit 1 RHR [Residual Heat Removal] shutdown cooling isolation valves 1E11-F008 and 1E11-F009 need to be de-energized in order to preclude the opening of these valves should this vulnerability occur on Unit 1. Since the Unit 2 RHR shutdown cooling isolation valves 2E11-F008 and 2E11-F009 are already closed and deactivated, they are not presently impacted by this additional vulnerability.
Immediate actions were taken to de-energize the valves in the 'closed' position which removed the vulnerability. The postulated intersystem LOCA represents an unanalyzed condition that significantly degraded plant safety. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+0.87 h0.0363 days <br />0.00518 weeks <br />0.00119 months <br />) | |
| Opened: | Kenny Hunter 21:32 Dec 4, 2013 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Dec 4, 2013 |
| 49607 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 526502017-03-30T13:22:00030 March 2017 13:22:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Potential Tornado Generated Missiles ENS 525312017-02-03T19:58:0003 February 2017 19:58:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Appendix R Fire Analysis ENS 511202015-06-04T14:03:0004 June 2015 14:03:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for a Postulated Fire ENS 510702015-05-14T20:00:00014 May 2015 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Excessive Toxic Chemicals Onsite ENS 506622014-12-09T23:25:0009 December 2014 23:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Non-Functional Fire Barrier Discovered Affecting Both Safe Shutdown Paths ENS 506292014-11-19T21:18:00019 November 2014 21:18:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Penetration Not Meeting Requirements ENS 504552014-09-13T07:07:00013 September 2014 07:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Penetration Did Not Meet Appendix R Requirements ENS 503512014-08-07T21:07:0007 August 2014 21:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Discovery of Degraded Fire Barrier Walls ENS 509982014-08-07T21:07:0007 August 2014 21:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition This Is a Continuation of En #50351 ENS 510912014-08-07T21:07:0007 August 2014 21:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition This Is a Continuation of En #50351 and En #50998 ENS 501602014-05-30T20:10:00030 May 2014 20:10:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Grouting in Fire Penetrations Does Not Meet Requirements ENS 499152014-03-14T15:55:00014 March 2014 15:55:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 496072013-12-04T20:40:0004 December 2013 20:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition a Potential Electrical Hot Short in the Rhr Shutdown Cooling Control Cable Could Result in an Inter-System Loca ENS 492852013-08-15T20:10:00015 August 2013 20:10:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition a Hot Short in the Rhr Shutdown Cooling Control Cable Could Result in an Inter-System Loca ENS 439922008-02-18T06:20:00018 February 2008 06:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to #2 Turbine Bypass Valve Failure ENS 435032007-07-18T16:20:00018 July 2007 16:20:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Unanalyzed Condition - Vent Space Less than Design Basis ENS 434992007-07-17T12:00:00017 July 2007 12:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Vent Space Less than Design Basis 2017-03-30T13:22:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_49607&oldid=422643"