ENS 49902
ENS Event | |
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18:00 Mar 12, 2014 | |
Title | |
Event Description | A review of industry operating experience (NRC Event Number 49889) regarding the impact of unfused Direct Current (DC) circuits has determined the described condition to be applicable to Millstone Power Station Unit 2 (MPS2) resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements.
In the postulated event, a fire induced hot short could adversely impact safe shutdown equipment. The MPS2 Main Turbine Emergency Lube Oil pump control and indication circuits route to the main control room. It is postulated that a fire in one fire area can damage this cable and cause short circuits without protection that would overheat the cable and possibly result in secondary fires in other fire areas where the cables are routed. The secondary fire 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. Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B). The NRC Resident Inspector has been notified. The licensee notified the State of Connecticut and the town of Waterford. |
Where | |
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Millstone Connecticut (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
LER: | 05000336/LER-2014-002 |
Time - Person (Reporting Time:+-1.55 h-0.0646 days <br />-0.00923 weeks <br />-0.00212 months <br />) | |
Opened: | Todd Perkins 16:27 Mar 12, 2014 |
NRC Officer: | Howie Crouch |
Last Updated: | Mar 12, 2014 |
49902 - NRC Website | |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 566102023-07-06T16:32:0006 July 2023 16:32:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 555762021-11-14T16:50:00014 November 2021 16:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition NON-FUNCTIONAL Steam Supply Check Valve to Turbine Driven Auxiliary Feedwater Pump ENS 555652021-11-06T15:00:0006 November 2021 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Steam Supply Check Failure to Turbine Driven Auxillary Feedwater ENS 499022014-03-12T18:00:00012 March 2014 18:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to a Postulated Hot Short That Could Affect Safe Shutdown Equipment ENS 499032014-03-12T18:00:00012 March 2014 18:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to a Postulated Hot Short That Could Affect Safe Shutdown Equipment ENS 494872013-10-30T19:25:00030 October 2013 19:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversly Impact Safe Shutdown Equipment ENS 490472013-05-17T08:39:00017 May 2013 08:39:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Reactor Coolant System Temperature Below Required Value ENS 444502008-08-29T14:07:00029 August 2008 14:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Related to Certain Fire Conditions ENS 437192007-10-12T17:30:00012 October 2007 17:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Affecting Fire Safe Shutdown ENS 436752007-09-28T21:00:00028 September 2007 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Vessel Head Vent May Not Be Isolable During a Fire 2023-07-06T16:32:00 | |