ENS 47413
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ENS Event | |
|---|---|
22:00 Nov 3, 2011 | |
| Title | Diesel Generator Starting Air Not Compliant with Appendix R Requirements |
| Event Description | During the conduct of a system vulnerability assessment by Engineering on the emergency diesel system. a discussion was held regarding the impact of a fire on the DG starting air system.
Subsequently it was recognized that components of the system were vulnerable to damage during a fire. A review of the Appendix R analysis was conducted and it was determined that this vulnerability was not analyzed in the evaluation. This is reportable to Unit 2, as Unit 1 has a separate diesel building for the 1-Alpha emergency diesel. The NRC Resident Inspector has been notified.
The Appendix R analysis was updated and no changes to the plant or procedures resulted. Therefore, no unanalyzed condition that significantly degraded plant safety existed. This event is being retracted. The NRC Resident Inspector has been notified. R1DO (Joustra) notified. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+1.43 h0.0596 days <br />0.00851 weeks <br />0.00196 months <br />) | |
| Opened: | Dan Geneva 23:26 Nov 3, 2011 |
| NRC Officer: | Charles Teal |
| Last Updated: | Dec 29, 2011 |
| 47413 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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 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 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 2018-05-14T17:05:00 | |
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