ENS 50455
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ENS Event | |
|---|---|
07:07 Sep 13, 2014 | |
| Title | Fire Penetration Did Not Meet Appendix R Requirements |
| Event Description | A fire penetration on the Unit 1 reactor building 158 foot elevation was discovered to be degraded such that the associated wall would not meet Appendix R requirements as a 3-hour barrier. In the event of a postulated fire in either of the affected fire areas, separated by the affected penetration, both Unit 1 safe shutdown paths could be compromised. Given this information, the determination was made that this condition meets the reporting criteria of 10CFR50.72(b)(3)(ii)(B).
Compensatory measures were established in accordance with the plant's Fire Hazard Analysis (FHA). The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded condition can be corrected. Condition Report: 865615 The NRC Resident Inspector has been informed. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+2.77 h0.115 days <br />0.0165 weeks <br />0.00379 months <br />) | |
| Opened: | Stanley Stone 09:53 Sep 13, 2014 |
| NRC Officer: | Charles Teal |
| Last Updated: | Sep 13, 2014 |
| 50455 - NRC Website
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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 | |
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