ENS 53239
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ENS Event | |
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22:43 Mar 1, 2018 | |
Title | Potential Tornado Missile Vulnerabilities |
Event Description | During review of protection of equipment from damaging effects of tornados, Point Beach Nuclear Plant identified a potential vulnerability for the turbine driven auxiliary feedwater pumps due to steam supply piping that is not routed through a Class 1 structure. Immediate compensatory measures were taken to mitigate the potential consequences of a tornado generated missile impact.
This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) and per 10 CFR 50.72(b)(3)(v)(A) and (D). The identified vulnerability is being addressed in accordance with EGM 15-002 and DSS-ISG-2016-01, enforcement discretion memorandum and interim guidance document for resolution of noncompliance with tornado-generated missile protection. The NRC Resident Inspector has been notified. |
Where | |
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Point Beach ![]() Wisconsin (NRC Region 3) | |
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)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+-2.63 h-0.11 days <br />-0.0157 weeks <br />-0.0036 months <br />) | |
Opened: | Rick Robbins 20:05 Mar 1, 2018 |
NRC Officer: | Howie Crouch |
Last Updated: | Mar 1, 2018 |
53239 - 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 %) |
Point Beach ![]() | |
WEEKMONTHYEARENS 532392018-03-01T22:43:0001 March 2018 22:43:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 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 Potential Tornado Missile Vulnerabilities ENS 529762017-09-18T22:24:00018 September 2017 22:24:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 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 Room Envelope Not Maintained ENS 507402015-01-15T23:04:00015 January 2015 23:04:00 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 Inadequately Sealed Piping Penetrations and Postulated Flooding Event ENS 502622014-07-08T05:24:0008 July 2014 05:24:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Unit 2 Spray Addition Declared Inoperable Due to Tank Indication Greater than 67% ENS 489212013-04-14T11:20:00014 April 2013 11:20:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Containment Spray Chemical Addition Flow Path Isolated ENS 484022012-10-12T09:20:00012 October 2012 09:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Power Exceeded Fsar Analyzed Value ENS 466462011-02-28T03:59:00028 February 2011 03:59:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Degraded Accident Mitigation Due to Safety Injection Out of Service ENS 443512008-07-16T20:16:00016 July 2008 20:16:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Fire Propagation Between Rooms Could Affect Appendix R Safe Shutdown ENS 437502007-10-26T00:30:00026 October 2007 00:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Low Temperature Overpressure Protection Systems Out of Service ENS 434872007-07-12T15:15:00012 July 2007 15:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Inspection Analysis of Pressurizer Porvs and Block Valves ENS 433532007-05-09T21:23:0009 May 2007 21:23:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Identified Non Compliant Fire Protection Manual Operator Actions ENS 431492007-02-06T20:15:0006 February 2007 20:15:00 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)(A), Seriously Degraded Control Room Emergency Filtration System Declared Inoperable ENS 430402006-12-09T00:12:0009 December 2006 00:12:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Crefs System Inoperable ENS 426112006-05-30T14:23:00030 May 2006 14:23:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Emergency Filtration System Inoperable ENS 421292005-11-08T14:44:0008 November 2005 14:44:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Design Basis for Long Term Cooling Not Correctly Modeled ENS 421092005-11-02T05:00:0002 November 2005 05:00:00 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)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Degradation of Containment Coatings ENS 420202005-09-27T15:00:00027 September 2005 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Faults Have Electrical Current in Excess of the Maximum Listed Interrupting Ratings. ENS 418852005-08-02T01:00:0002 August 2005 01:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Potentially Inoperable Safety Injection Pumps ENS 418562005-07-20T09:51:00020 July 2005 09:51:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Minimum Recirculation Valves Will Not Automatically Open in Local Operating Mode ENS 417582005-06-08T22:24:0008 June 2005 22:24:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Fire Organizational Plan No Longer Aligned with Safe Shutdown Analysis ENS 417542005-06-07T23:00:0007 June 2005 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Appendix R Safe Shutdown Strategy Deficiency 2018-03-01T22:43:00 | |
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