ENS 49889
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ENS Event | |
|---|---|
20:53 Mar 10, 2014 | |
| Title | Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment |
| Event Description | An extent of condition review identified that there were unfused 250 VDC circuits for the battery charger ammeters and the control circuits for various DC lube oil pumps which left the turbine building and went through the respective cable spreading room and up into the Control Room. These circuits are protected by 200 amp fuses and in some cases 100 amp fuses. The concern is that under the fire safe shutdown rules, it is postulated that a fire in one fire area can damage these circuits and cause short circuits without protection that would overheat the cables and possibly result in secondary fires in other fire areas where the cables are routed. The secondary fires could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.
This condition is reportable as an 8-hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| LER: | 05000336/LER-2014-002 05000423/LER-2014-002 |
| Time - Person (Reporting Time:+1.83 h0.0763 days <br />0.0109 weeks <br />0.00251 months <br />) | |
| Opened: | James Grooms 22:43 Mar 10, 2014 |
| NRC Officer: | Charles Teal |
| Last Updated: | Mar 10, 2014 |
| 49889 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
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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