ENS 53438
ENS Event | |
|---|---|
04:00 Jun 1, 2018 | |
| Title | Tornado Missile Vulnerabilities |
| Event Description | During the period of evaluation of tornado missile vulnerabilities and the potential impacts to technical specification (TS) plant equipment, it was determined that the power cables to a safety related motor control center (MCC) in the service water (SW) intake structure are not adequately protected from tornado generated missiles. During walk downs, it was identified that the installed SW pipe tunnel barrier is not adequate. A tornado could generate missiles capable of striking the power cables and rendering a SW MCC inoperable.
These conditions are reportable per 10 CFR 50.72(b)(3)(ii)(B) and per 10 CFR 50.72(b)(3)(v)(D). This condition is being addressed in accordance with NRC enforcement guidance provided in Enforcement Guidance Memorandum (EGM) 15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado- Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents. The NRC Resident Inspector has been notified. The licensee will be notifying the Lower Alloways Creek Township.
During subsequent walk downs, PSEG [Public Service Enterprise Group] identified that both the Unit 1 and Unit 2 turbine driven auxiliary feedwater pumps are also not adequately protected from tornado generated missiles. The steam exhaust pipe could be potentially impacted and cause crimping that could reduce steam exhaust flow and pump capacity. EN 53438 is updated to include both Salem units and these additional components. This condition is being addressed in accordance with NRC enforcement guidance provided in enforcement Guidance Memorandum (EGM)15-002, 'Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1, and DSS-ISG-2016-01, 'Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,' Revision 1. Compensatory measures have been implemented in accordance with these documents." The NRC Resident Inspector has been notified. The licensee will be notifying the Lower Alloways Creek Township. Notified R1DO (Burritt). |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+10.7 h0.446 days <br />0.0637 weeks <br />0.0147 months <br />) | |
| Opened: | Matthew D. Mog 14:42 Jun 1, 2018 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Jun 19, 2018 |
| 53438 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Salem with 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 | |
WEEKMONTHYEARENS 534382018-06-01T04:00:0001 June 2018 04:00:00
[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 Tornado Missile Vulnerabilities ENS 522942016-10-11T13:38:00011 October 2016 13:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Failure of a Watertight Door to Close ENS 522222016-09-03T13:02:0003 September 2016 13:02:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unidentified Leakage Greater than Technical Specifications ENS 519022016-05-03T17:01:0003 May 2016 17:01:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Anomalies Identified During Visual Inspection of Reactor Vessel Internals ENS 516632016-01-19T21:30:00019 January 2016 21:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Discovered During Review of Outage Data ENS 515632015-11-24T02:48:00024 November 2015 02:48:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Reactor Coolant System Leakage ENS 515042015-10-28T10:28:00028 October 2015 10:28:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Trains of Control Room Emergency Air Conditioning System Inoperable ENS 513492015-08-26T16:15:00026 August 2015 16:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Appendix R Postulated Fire ENS 511702015-06-22T18:06:00022 June 2015 18:06:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Sodium Hydroxide Below Technical Specification Required Concentration ENS 505732014-10-29T11:11:00029 October 2014 11:11:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Control Room Emergency Air Conditioning System Operability ENS 504052014-08-27T06:48:00027 August 2014 06:48:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Safety Injection Pump Failed to Start ENS 496992014-01-07T12:45:0007 January 2014 12:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Caused by High Energy Line Break Barrier Door Open During Maintenance ENS 495392013-11-14T18:22:00014 November 2013 18:22:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 489492013-04-20T08:22:00020 April 2013 08:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System ENS 480712012-07-05T14:00:0005 July 2012 14:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Valve Improperly Aligned for Accident Mitigation ENS 441202008-04-04T16:59:0004 April 2008 16:59:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System ENS 430382006-12-07T22:28:0007 December 2006 22:28:00 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 Loss of Safe Shutdown Capability ENS 415252005-03-25T01:15:00025 March 2005 01:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Coolant Leakage Outside Containment Exceeding Design Basis ENS 411182004-10-13T19:41:00013 October 2004 19:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Coolant Leakage Outside Containment Exceeding Final Safety Analysis Limits ENS 407802004-05-27T10:30:00027 May 2004 10:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Automatic Safety Injection Function Inadvertantly Blocked ENS 406702004-04-12T14:33:00012 April 2004 14:33:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System ENS 404802004-01-25T22:00:00025 January 2004 22:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Differential Pressure in Auxiliary Building 2018-06-01T04:00:00 | |