ENS 41383
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ENS Event | |
|---|---|
01:23 Feb 8, 2005 | |
| Title | Manual Reactor Trip During Startup Due to Indication of Misaligned Rod |
| Event Description | The following information was provided by the licensee via facsimile:
While withdrawing Control Bank 'A' during the Reactor Startup, Rod B-10 indicated a rapid drop from approximately 42 steps to 17 steps on the CERPI (Computer Enhanced Rod Position Indication) panel. The reactor operator stopped withdrawal of 'A' control bank and the CERPI indication for rod B-10 remained at 17 steps. The remaining CERPIs in 'A' control bank varied from 40 to 45 steps. The startup was terminated and the reactor was manually tripped in accordance with AP-1 and 1-E-0 [was] initiated. All systems functioned as required on the trip. Initial investigation by I & C and Engineering found no problems with the CERPI indication. Rod Drop time data from the CERPI program shows all rods in Control Bank 'A' had a drop time of 0.32 to 0.38 seconds with the exception of B-10, which had a drop time of 0.18 seconds. An investigation is ongoing as to the cause of rod B-10 misalignment. This notification is being made pursuant to 10 CFR 50.72(b)(3)(iv)(A). The NRC resident was notified of this event. The reactor was subcritical in the Source Range at the initiation of the event. All rods inserted fully during the manual reactor trip. S/G level is being maintained by main feedwater and decay heat removal is via the S/G PORV. |
| Where | |
|---|---|
Surry  Virginia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.15 h-0.0479 days <br />-0.00685 weeks <br />-0.00158 months <br />) | |
| Opened: | David Herring 00:14 Feb 8, 2005 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Feb 8, 2005 |
| 41383 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | Yes, Manual Scram |
| Before | Startup (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 537362018-11-12T05:00:00012 November 2018 05:00:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 536622018-10-11T04:00:00011 October 2018 04:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Emergency Diesel Generator Due to Transformer Trip ENS 531702018-01-17T14:52:00017 January 2018 14:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auto-Start of Emergency Diesel Generator Due to Transformer Fuses Being Disconnected ENS 522922016-10-09T06:54:0009 October 2016 06:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Main Generator Differential Lockout Turbine Trip ENS 514672015-10-13T22:15:00013 October 2015 22:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip After a Turbine Trip ENS 514022015-09-17T00:14:00017 September 2015 00:14:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start and Loading of the #2 Emergency Diesel Generator ENS 505292014-10-13T11:58:00013 October 2014 11:58:00 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 a Spurious Overpower / Delta Temperature Signal ENS 486382012-12-29T13:03:00029 December 2012 13:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Auto-Start and Load Upon Trip of Reserve Station Transformer ENS 469052011-05-30T12:08:00030 May 2011 12:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Afw Initiation ENS 467612011-04-16T22:55:00016 April 2011 22:55:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 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 Loss of All Offsite Power from Tornado Damage ENS 465842011-02-02T10:33:0002 February 2011 10:33:00 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 Loss of Rcs Coolant Flow in One Loop ENS 459862010-06-08T13:48:0008 June 2010 13:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip with Safety Injection Due to Loss of Vital Ac Bus ENS 442212008-05-17T13:04:00017 May 2008 13:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Failed Relay Causes Emergency Diesel Generator to Start ENS 441522008-04-21T02:16:00021 April 2008 02:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manual Reactor Trip Due to Main Turbine Vibrations ENS 413832005-02-08T01:23:0008 February 2005 01:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Startup Due to Indication of Misaligned Rod ENS 407692004-05-22T01:08:00022 May 2004 01:08:00 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 Generator Leads Failure ENS 401682003-09-18T13:00:00018 September 2003 13:00:00 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 Expected Severe Weather 2018-11-12T05:00:00 | |
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