ENS 43675
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ENS Event | |
|---|---|
21:00 Sep 28, 2007 | |
| Title | Reactor Vessel Head Vent May Not Be Isolable During a Fire |
| Event Description | Plant engineering determined that in a postulated fire in the Control Room or Cable Spreading Room which required Control Room evacuation, that "hot shorts" may prevent the reactor vessel head vents from performing their emergency functions in accordance with the plant Emergency Operating Procedures (EOPs). Several relays in the letdown system are not isolated at the Auxiliary Shutdown Panel and have the potential for shorting during a fire. This letdown path can be aligned from the reactor vessel head vents during certain EOP scenarios.
The affected reactor vessel head vent isolation transfer switches are: 3RCS*SV8095A & B and 3RCS*SV8096A & B. The site has implemented an hourly fire watch in the affected areas. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Millstone  Connecticut (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+-2.25 h-0.0938 days <br />-0.0134 weeks <br />-0.00308 months <br />) | |
| Opened: | Brien Strizzi 18:45 Sep 28, 2007 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Sep 28, 2007 |
| 43675 - NRC Website
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Unit 3 | |
|---|---|
| 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 | |
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