ENS 52817
ENS Event | |
|---|---|
15:00 Jun 21, 2017 | |
| Title | Postulated Fire Event Could Adversely Impact Safe Shutdown Equipment |
| Event Description | During the review of an electrical circuit coordination calculation to support an ongoing revision of the Fire Safe Shutdown Analysis (FSSA), a lack of appropriate circuit protection coordination was identified in the coordination of electrical protective devices on 118 VAC electrical panels operating in bypass mode of operation.
One or more of these electrical panels could be lost for various 10 CFR Appendix R III.G.2 fires outside the Control Room at CPNPP [Comanche Peak Nuclear Power Plant] due to circuit coordination issues. This could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. Immediate compensatory actions are being taken to establish (or confirm already existing) fire watches in the Fire Areas containing the associate circuits which can potentially jeopardize the FSSA. This condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. The NRC Resident Inspector has been notified.
On 06/21/2017 Comanche Peak reported an ENS Report (no. 52817) related to the potential loss of 118 VAC electrical panels operating in bypass mode of operation for various 10 CFR [50] Appendix R III.G.2 fires outside the Control Room due to circuit coordination issues. This could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. Subsequent analysis by Engineering has determined that the affected panels remain coordinated for fire generated faults and can be credited as available by the Fire Safe Shutdown Analysis for a fire outside of the Control Room. Based on the above, the condition described in the ENS report no. 52817 is not considered to be an unanalyzed condition as described in 10 CFR 50.72(b)(3)(ii)(B). The licensee notified the NRC Resident Inspector. Notified R4DO (Azua). |
| Where | |
|---|---|
Comanche Peak  Texas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+1.42 h0.0592 days <br />0.00845 weeks <br />0.00195 months <br />) | |
| Opened: | Robert Daniels 16:25 Jun 21, 2017 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Aug 2, 2017 |
| 52817 - 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 | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 528172017-06-21T15:00:00021 June 2017 15:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Fire Event Could Adversely Impact Safe Shutdown Equipment ENS 526462017-03-29T00:57:00029 March 2017 00:57:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for a Postulated Moderate Energy Line Break ENS 524842017-01-11T21:00:00011 January 2017 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Teflon Found in Containment Spray Pump Components ENS 522442016-09-15T20:40:00015 September 2016 20:40:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 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 Potential Degradation of Eccs Pump Pressure Indicators ENS 522392016-09-13T22:30:00013 September 2016 22:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Station Service Water Trains ENS 522172016-09-01T15:25:0001 September 2016 15:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition on Turbine Driven Auxiliary Feedwater Pump ENS 517512016-02-23T23:00:00023 February 2016 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Normally Open Battery Room Doors ENS 508352015-02-19T22:00:00019 February 2015 22:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Normally Closed Watertight Doors ENS 500432014-04-18T17:52:00018 April 2014 17:52:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Cable Routing Unanalyzed for Fire Safe Shutdown Barrier ENS 494192013-10-08T17:40:0008 October 2013 17:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 477132012-03-01T23:05:0001 March 2012 23:05:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Battery Room Ventilation System Degraded ENS 473572011-10-20T01:02:00020 October 2011 01:02:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Pressure Instruments Containing Aluminum Material ENS 473522011-10-18T20:45:00018 October 2011 20:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Aluminum Valve Discovered Installed in Containment ENS 470862011-07-21T16:53:00021 July 2011 16:53:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Vulnerability from a Potential Control Room Fire on "a" Safeguards Bus ENS 435622007-08-13T14:00:00013 August 2007 14:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Inadequate Fire Protection on Safety Chilled Water System Electrical Cables 2017-06-21T15:00:00 | |