ENS 47316
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
14:35 Oct 3, 2011 | |
| Title | Technical Specification (Ts) Required Shutdown Due to Both 'A' Train Edg'S Inoperable |
| Event Description | Dual Unit Shutdown due to T.S. 3.0.3. Unit 1 and Unit 2 'A' Train Emergency Diesel Generators (EDGs) OOS [Out-of-Service]. '2A' DG OOS due to '21' Salt Water Header scheduled maintenance. '1A' DG OOS due to emergent loss of '16' Battery charger for the '1A' DG DC bus. Neither '11' nor '22' 125 VDC busses have an Operable charger. (Chargers have power, but do not have an Operable DG). "
The licensee entered TS 3.0.3 at 1035 EDT and is expected to be in Mode 3 on both units at 1735 EDT unless the licensee exits T.S. 3.0.3 upon restoration of the battery charger. '0C' EDG is functional but not credited towards T.S. The salt water header is not expected to be restored until 10/4/11. There are no issues with offsite power. The NRC Resident Inspector has been notified. The licensee will notify the Calvert Control Center and plans to make a press release. CR No.: CR-2011-009860; Calvert Cliffs internal event notification number 4194. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.17 h0.00708 days <br />0.00101 weeks <br />2.32866e-4 months <br />) | |
| Opened: | Kevin Umphrey 14:45 Oct 3, 2011 |
| NRC Officer: | Joe O'Hara |
| Last Updated: | Oct 3, 2011 |
| 47316 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (60 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (67 %) |
Calvert Cliffs with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 551222021-03-04T08:23:0004 March 2021 08:23:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Notification of Degraded Condition ENS 543252019-10-11T17:00:00011 October 2019 17:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Initiated ENS 517472016-02-20T08:30:00020 February 2016 08:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Pressurizer Safety Relief Valve Weld ENS 503072014-07-25T03:15:00025 July 2014 03:15:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage ENS 493232013-09-05T17:14:0005 September 2013 17:14:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Failure to Align Control Element Assembly During Testing ENS 487632013-02-17T18:45:00017 February 2013 18:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Discovered During Containment Walkdown ENS 481832012-08-12T16:34:00012 August 2012 16:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Fully Inserted Control Rod While Operating ENS 481242012-07-21T16:10:00021 July 2012 16:10:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Rcs Pressure Boundary Instrument Line Leakage ENS 481162012-07-17T04:00:00017 July 2012 04:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Small Rcs Pressure Boundary Instrument Line Leak ENS 473162011-10-03T14:35:0003 October 2011 14:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification (Ts) Required Shutdown Due to Both 'A' Train Edg'S Inoperable ENS 466232011-02-18T05:51:00018 February 2011 05:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Inactive Leak Identified on Presurizer Heater Well ENS 457372010-03-02T12:30:0002 March 2010 12:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressurizer Safety Nozzle Weld Degradation ENS 457192010-02-23T20:12:00023 February 2010 20:12:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Weld Leak Due to Vibrating Valve Attachment Wire ENS 440062008-02-25T06:40:00025 February 2008 06:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Leakage on a Pressurizer Heater Sleeve ENS 424842006-04-09T03:42:0009 April 2006 03:42:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Control Element Assembly Stuck During Physics Testing ENS 414482005-02-27T20:00:00027 February 2005 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld ENS 414452005-02-26T20:30:00026 February 2005 20:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld 2021-03-04T08:23:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_47316&oldid=424330"