ENS 49968
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ENS Event | |
|---|---|
17:00 Mar 28, 2014 | |
| Title | Keowee Emergency Power System 13.8Kv Cable May Not Comply with Licensing Basis |
| Event Description | Event: In an NRC Component Design Basis Inspection (CDBI) debrief held at 1300 EDT on March 28, 2014, it was stated that a potential non-compliance and unanalyzed condition exists with respect to the design and installation of the Keowee emergency power system 13.8kV power cables associated with the underground power path. The NRC stated that Duke does not have sufficient documentation to support the station's position that the cables comply with the station's licensing basis. In particular, there are questions related to the station's compliance with IEEE-279-1971. This issue has been documented in Duke's corrective action program.
Duke has reviewed the design associated with the subject 13.8kV cables and considers the design to be robust. Pending further analysis and/or testing, Duke has made a decision to report this event in accordance with 10 CFR 50.72(b)(3)(ii) as an 'Unanalyzed Condition.' The Oconee NRC Senior Resident Inspector has been notified of the event. Initial Safety Significance: An Immediate Determination of Operability has been performed and concluded the existing system design is adequately robust to address circuit faults. The health and safety of the public and station personnel is not impacted by this event. Corrective Action(s): Corrective actions are being implemented in accordance with Duke's Corrective Action Program. |
| Where | |
|---|---|
Oconee  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-0.65 h-0.0271 days <br />-0.00387 weeks <br />-8.9037e-4 months <br />) | |
| Opened: | Kevin Moses 16:21 Mar 28, 2014 |
| NRC Officer: | Dong Park |
| Last Updated: | Mar 28, 2014 |
| 49968 - 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 (100 %) |
| After | Power Operation (100 %) |
Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 506402014-11-25T17:12:00025 November 2014 17:12:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Deficiency in Methodology Used for Emergency Core Cooling System Performance Requirements ENS 499682014-03-28T17:00:00028 March 2014 17:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Keowee Emergency Power System 13.8Kv Cable May Not Comply with Licensing Basis ENS 490682013-05-24T18:00:00024 May 2013 18:00:00 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 Heating Ventilation and Air Condition System Inadequately Analyzed for Heat Load ENS 478102012-04-06T02:38:0006 April 2012 02:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Standby Shutdown Facility (Ssf) Not Analyzed for All Operating Conditions ENS 423182006-02-07T01:50:0007 February 2006 01:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Non-Conforming Fire Barriers ENS 418502005-07-18T15:30:00018 July 2005 15:30:00 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 Electrical Alignment Results in Single Failure Vulnerability ENS 417282005-05-24T17:50:00024 May 2005 17:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Emergency Backup Power Generators ENS 407242004-05-04T20:55:0004 May 2004 20:55:00 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 Unanalyzed Condition and Potential Loss of Containment Safety Function ENS 401922003-09-23T08:00:00023 September 2003 08:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Potential Rcs Leakage at Oconee 1 2014-03-28T17:00:00 | |
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