ENS 53401
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ENS Event | |
|---|---|
17:05 May 14, 2018 | |
| Title | Saltwater System Non-Conforming with Licensing Basis for Tornado Generated Missiles |
| Event Description | On May 14, 2018, during evaluation of protection for Technical Specification (TS) equipment from the damaging effects of a tornado generated missile, Calvert Cliffs identified a non-conforming condition in the plant design such that specific TS equipment is considered to not be adequately protected from a tornado generated missile. A tornado could generate a missile that could strike the Unit 1 Saltwater system header and associated piping. This could result in damage to the unit 1 Saltwater system header which could affect the ability of the Unit 1 Saltwater subsystems to perform their design function if such a tornado would occur.
This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(D) for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. This condition is being addressed in accordance with NRC enforcement guidance provided in EGM 15-002 and DSS-ISG-2016-01. Compensatory measures have been implemented in accordance with these documents. The NRC Resident Inspector has been informed of this notification. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+-3.8 h-0.158 days <br />-0.0226 weeks <br />-0.00521 months <br />) | |
| Opened: | Dan Geneva 13:17 May 14, 2018 |
| NRC Officer: | Donald Norwood |
| Last Updated: | May 14, 2018 |
| 53401 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Calvert Cliffs 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 536632018-10-11T04:00:00011 October 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 Air Start Solenoid Closure Failure ENS 534932018-07-07T04:00:0007 July 2018 04:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Ventilation Inoperable ENS 534012018-05-14T17:05:00014 May 2018 17:05:00 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 Saltwater System Non-Conforming with Licensing Basis for Tornado Generated Missiles ENS 526402017-03-25T05:42:00025 March 2017 05:42:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Refueling Water Tank Level Inadvertently Lowered Below Ts ENS 509612015-04-07T16:45:0007 April 2015 16:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 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)(iv)(A), System Actuation Dual Unit Automatic Reactor Trips Due to a Voltage Transient Resulting in Generator Trips ENS 507522015-01-22T22:45:00022 January 2015 22:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Heat Exchanger Lineup Could Exceed Design Basis Temperatures ENS 498892014-03-10T20:53:00010 March 2014 20:53:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 494492013-10-18T12:30:00018 October 2013 12:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 483672012-10-03T04:10:0003 October 2012 04:10:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to High Energy Line Break Barrier Being Partially Open ENS 476192012-01-23T18:00:00023 January 2012 18:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Breach in High Energy Line Break Barrier ENS 475122011-12-08T22:55:0008 December 2011 22:55:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Potentially Could Affect the Common Control Room ENS 474132011-11-03T22:00:0003 November 2011 22:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Diesel Generator Starting Air Not Compliant with Appendix R Requirements ENS 438302007-12-08T05:50:0008 December 2007 05:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Power Inadvertently Increased Above Accident Analysis Limit ENS 431092007-01-20T08:38:00020 January 2007 08:38:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Crevs and Crets Inoperable Due to 1A and 2B Edg Oos 2018-07-07T04:00:00 | |
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