ENS 50324
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ENS Event | |
|---|---|
14:40 Jul 30, 2014 | |
| Title | |
| Event Description | On July 30, 2014, at [0940 CDT], with the plant operating at 100% power, a review of an engineering analysis of the ultimate heat sink (UHS) determined that the UHS had been in an unanalyzed condition that degraded plant safety. This condition was the result of a design basis deficiency for the UHS that did not account for the adverse effects of system leakage on compliance with the 30-day inventory required by Regulatory Guide 1.27. The system design basis requires that 30-day inventory be maintained, with the assumption that no replenishment of the UHS occurs for the entire duration of the postulated event.
In support of the development of the engineering analysis, compensatory measures have been implemented which provide adequate assurance that the UHS will perform its design safety function. Corrective actions to restore full compliance with design basis requirements are in development. This event is being reported in accordance with 10 CFR 50.72 (b)(3)(ii) as an unanalyzed condition that degraded the safety function of the UHS. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
River Bend  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-1.22 h-0.0508 days <br />-0.00726 weeks <br />-0.00167 months <br />) | |
| Opened: | Jack Mccoy 13:27 Jul 30, 2014 |
| NRC Officer: | Vince Klco |
| Last Updated: | Jul 30, 2014 |
| 50324 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 536222018-09-25T05:00:00025 September 2018 05:00:00
[Table view]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 Control Building Chillers in Unanalyzed Condition ENS 533822018-05-04T16:29:0004 May 2018 16:29:00 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)(ii)(B), Unanalyzed Condition Unanalyzed Condition Associated with Damaging Effects of Tornados ENS 533242018-04-11T06:50:00011 April 2018 06:50:00 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 Condition That Could Impair Function of Control Building Ac System ENS 525682017-02-20T18:40:00020 February 2017 18:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Potential Failure of Control Room and Control Building Air Handling Units ENS 503242014-07-30T14:40:00030 July 2014 14:40:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Ultimate Heat Sink in an Unanalyzed Condition ENS 497052014-01-09T06:00:0009 January 2014 06:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Identified from Operating Experience Review ENS 433792007-05-21T17:31:00021 May 2007 17:31:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Division 1 Edg Damage Due to Loss of Service Water Cooling During Control Room Fire ENS 422432006-01-05T15:30:0005 January 2006 15:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Involving Rcic Operation During Mcr Evacuation 2018-09-25T05:00:00 | |
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