ENS 52531
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ENS Event | |
|---|---|
19:58 Feb 3, 2017 | |
| Title | Unanalyzed Condition - Appendix R Fire Analysis |
| Event Description | In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10CFR50.48(b) (Appendix R) to 10CFR50.48(c) (NFPA 805), a weak-link and operator manual action (OMA) analysis for Information Notice (IN) 92-18 type hot shorts on motor-operated valves (MOVs) was performed to support the Plant Hatch Appendix R Safe Shutdown Analysis. As a result of the analysis, it was identified that cable impacts can bypass valve limit and torque switches, resulting in physical damage to valves required for Safe Shutdown. This would prevent the valves from being operated locally or being operated from the remote shutdown panel. These cable failures could also cause the valve motors to fail. This updated analysis has identified circuit configuration deficiencies in Fire Areas 0024 A & C (Main Control Room & Cable Spread Room), 1203F (U1 Reactor Building SE), 1205F (U1 Reactor Building NE), and 2203F (U2 Reactor Building NE). Therefore, due to the identified deficient conditions, it was determined that in the event of a postulated fire in the affected fire areas, the paths of safe shutdown on the affected unit(s) could be compromised and impact the ability to achieve safe shutdown conditions.
Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions in these same fire areas. 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 conditions can be repaired. CRs 10326399, 10326401, 10326402, 10326404 and 10326405 The licensee notified the NRC Resident Inspector. The unanalyzed condition is applicable to 10CFR50.48(b) Appendix R and not to 10CFR50.48(c) (NFPA 805). |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-3.42 h-0.143 days <br />-0.0204 weeks <br />-0.00468 months <br />) | |
| Opened: | Jason Wiggins 16:33 Feb 3, 2017 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Feb 3, 2017 |
| 52531 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (88 %) |
| After | Power Operation (88 %) |
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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