ENS 41330
ENS Event | |
|---|---|
14:49 Jan 13, 2005 | |
| Title | Entry Into Technical Specification Required Shut Down Due to Loss of Essential Bus |
| Event Description | The following information was provided by the licensee via facsimile:
At 0849 hours0.00983 days <br />0.236 hours <br />0.0014 weeks <br />3.230445e-4 months <br /> on January 13, 2005, during testing of Essential Bus D1 (Undervoltage Units monthly functional test) [the] Potential Transformer secondary fuse blew. This caused an Essential 4160 VAC Bus D1 undervoltage condition. Emergency Diesel Generator #2 auto started due to the undervoltage condition on Essential Bus D1. This auto start of EDG #2 is reportable IAW [in accordance with] 10CFR50.72(b)(3)(iv)(a). [The licensee entered] into Technical Specification 3.0.3 with a loss of Essential 4160 VAC Bus D1 [with] plant shutdown required within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the Essential Bus and DC battery chargers 2P and 2N are not restored. At 0949 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />, [the licensee] commenced plant shutdown to comply with Technical Specification 3.0.3. The initiation of the plant shutdown is reportable IAW 10CFR50.72(b)(2)(i). [At] 1049 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.991445e-4 months <br />, [the license] re-energized Essential 4160 VAC Bus D1 and verified battery chargers 2P and 2N energized. [At]1051 hours, [the licensee] exited Technical Specification 3.0.3 and stopped plant shutdown. [The licensee also noted that] at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />, EDG #2 was shutdown when the #2 Service Water pump did not start. [At] 1144 hours0.0132 days <br />0.318 hours <br />0.00189 weeks <br />4.35292e-4 months <br />, Service Water Pump #2 [was started and the licensee] declared Service Water Loop 2 OPERABLE. The license has notified the NRC Resident Inspector, will notify local government agencies, and expects to make a press release. |
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000346/LER-2005-001 |
| Time - Person (Reporting Time:+-1.28 h-0.0533 days <br />-0.00762 weeks <br />-0.00175 months <br />) | |
| Opened: | Anthony Stallard 13:32 Jan 13, 2005 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jan 13, 2005 |
| 41330 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (95 %) |
Davis Besse with 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 562842022-12-23T20:13:00023 December 2022 20:13:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 557342022-02-05T20:14:0005 February 2022 20:14:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 522322016-09-10T07:43:00010 September 2016 07:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Unit Trip Due to Main Generator Lock-Out ENS 520792016-07-01T09:42:0001 July 2016 09:42:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Failure to Perform Technical Specification Required Shutdown ENS 517022016-01-30T06:23:00030 January 2016 06:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unanticipated Sfrcs Actuation While Restoring Main Feedwater to Steam Generators ENS 516962016-01-29T18:22:00029 January 2016 18:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Reactor Protection System Actuation ENS 510612015-05-09T22:55:0009 May 2015 22:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to Steam Leak in the Turbine Building ENS 500862014-05-05T18:56:0005 May 2014 18:56:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram with Rod Motion While Shutdown ENS 500972014-05-04T12:32:0004 May 2014 12:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of the Reactor Protection System While Shutdown ENS 413302005-01-13T14:49:00013 January 2005 14:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Entry Into Technical Specification Required Shut Down Due to Loss of Essential Bus ENS 402082003-10-01T01:34:0001 October 2003 01:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Specified System Actuation ENS 401612003-09-16T04:30:00016 September 2003 04:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Coolant System Pressure Increase Caused a Valid Signal 2022-02-05T20:14:00 | |