ENS 49068
ENS Event | |
---|---|
18:00 May 24, 2013 | |
Title | Heating Ventilation and Air Condition System Inadequately Analyzed for Heat Load |
Event Description | There is no current event in progress at Oconee Nuclear Station (ONS). This notification is [being made] to complete a required 10 CFR 50.72 report that was not made at the time of discovery. During a review of the guidance in NUREG 1022, Rev. 2, ONS recognized conditions that were reported to the NRC in LER 269/2013-001-00 on April 8, 2013, (ADAMS Accession ML13101A307), which met the 8-hour reporting requirements of 10 CFR 50.72(b)(3)(ii)(B) -- 'Unanalyzed Condition,' and 10 CFR 50.72(b)(3)(v)(A,B,C&D) -- 'Event or Condition That Could Have Prevented Fulfillment of a Safety Function,' but were not previously reported per 10 CFR 50.72(b)(3).
LER 269/2013-001-00 previously documented Duke Energy's conclusion that emergency power equipment could be adversely impacted by a licensee identified, original design issue involving inadequate analysis of electrical equipment heat loads and weaknesses in the Heating Ventilation and Air Conditioning (HVAC) system design. Nothing in this notification modifies or supplements the information provided in LER 269/2013-001-00. This legacy event notification completes the action required by 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(A,B,C&D). The need to perform a 10 CFR 50.72 notification was not recognized during the reportability evaluation. Initial Safety Significance: None. This is a legacy event notification. Oconee's emergency power equipment is currently operable, but nonconforming with Oconee's license. Corrective Action(s): Compensatory measures are in place, and modifications are in progress to address the legacy design issue. The issue of not reporting as required under 10 CFR 50.72(b)(3) is entered into Duke Energy's corrective action program. The Oconee NRC Resident Inspector has been notified. |
Where | |
---|---|
Oconee South Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 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)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
Time - Person (Reporting Time:+-3.22 h-0.134 days <br />-0.0192 weeks <br />-0.00441 months <br />) | |
Opened: | Bob Meixell 14:47 May 24, 2013 |
NRC Officer: | Charles Teal |
Last Updated: | May 24, 2013 |
49068 - NRC Website | |
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 %) |
Oconee with 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 | |
WEEKMONTHYEARENS 557132022-01-26T15:50:00026 January 2022 15:50:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Required Offsite and Both Onsite Emergency AC Power Paths Inoperable ENS 556122021-11-27T10:19:00027 November 2021 10:19:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the Emergency AC Electrical Power System ENS 528122017-06-16T20:35:00016 June 2017 20:35:00 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)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Loss of Safety Function Due to Keowee Dam Units Being Declared Inoperable ENS 506402014-11-25T17:12:00025 November 2014 17:12:00 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 491492013-06-26T14:40:00026 June 2013 14:40:00 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)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Inadvertent Closure of Opposite Train Valve Renders Safety Trains Inoperable 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 421712005-11-27T10:30:00027 November 2005 10:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Loss and Restoration of Back-Up Instrument Air to Feedwater Control Valves 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 416182005-04-20T20:10:00020 April 2005 20:10:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Both Penetration Room Ventilation System Trains Temporarily Inoperable ENS 412562004-12-13T05:00:00013 December 2004 05:00:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Containment Penetrations Not Closed During Fuel Handling Operations 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 2022-01-26T15:50:00 | |