ENS 43243
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ENS Event | |
|---|---|
02:09 Mar 17, 2007 | |
| Title | Automatic Reactor Trip Caused by Safety Injection Signal |
| Event Description | At 2209 on 3/16/07, the plant tripped on a Safety Injection (SI) signal initiated because of low main steam line pressure in the 'A' main steam loop. The licensee is currently conducting a post trip review but believes that the low main steam line pressure in 'A' loop was caused by a spurious isolation of the 'B' Main Steam Line Isolation Valve (MSIV). The isolation in the 'B' main steam loop lead to high main steam flow and low main steam line pressure in the 'A' main steam loop. The 'A' MSIV then also auto-closed on the SI signal.
The plant is currently stable in Mode 3 at about 2235 psig pressure and 547 degrees average Reactor Coolant System (RCS) temperature. All control rods fully inserted on the trip. Decay heat is currently being removed by auxiliary feedwater feeding the steam generators and steaming out the plant atmospheric steam valves. Since plant pressure did not decrease below 1500 psig, SI did not actually inject into the RCS. The licensee secured SI. No primary PORV's or safety valves lifted. No main steam safeties lifted according to plant closure indicators. There are no primary to secondary steam generator tube leaks. All electrical safeguards buses are powered by offsite power. The Emergency Diesel Generators (EDG) started but did not load and were shut down. The EDGs are operable and available if needed. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Ginna  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+0.07 h0.00292 days <br />4.166667e-4 weeks <br />9.5886e-5 months <br />) | |
| Opened: | Kyle Garnish 02:13 Mar 17, 2007 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Mar 17, 2007 |
| 43243 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Ginna with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 567902023-10-13T01:27:00013 October 2023 01:27:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 567312023-09-09T15:43:0009 September 2023 15:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 555042021-10-04T04:31:0004 October 2021 04:31:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid System Actuation ENS 536962018-10-26T04:00:00026 October 2018 04:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Automatic Start of the Emergency Diesel Generator and Loss of Radiation Monitor ENS 517302016-02-12T04:05:00012 February 2016 04:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Auto-Started Due to the Loss of a Station Service Transformer ENS 492142013-07-24T18:19:00024 July 2013 18:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from Full Power ENS 479882012-06-03T06:39:0003 June 2012 06:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Autostart of "B" Edg Due to Loss of Offsite Power Circuit 767 ENS 473382011-10-12T03:28:00012 October 2011 03:28:00 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 Turbine Auto Stop Valve Closure ENS 469172011-06-03T04:39:0003 June 2011 04:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unexpected Emergency Diesel Generator Actuation ENS 432432007-03-17T02:09:00017 March 2007 02:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Safety Injection Signal ENS 431282007-01-28T01:40:00028 January 2007 01:40:00 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 Load Transient Caused by Ehc Problem ENS 417652005-06-10T17:51:00010 June 2005 17:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Bus Due to a Lighting Strike with Actuation of Emergency Diesel Generator ENS 415582005-04-01T19:02:0001 April 2005 19:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Start Due to a Partial Loss of Offsite Power ENS 414142005-02-17T02:12:00017 February 2005 02:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Turbine Trip as a Result of Failed Power Supply ENS 403192003-11-13T14:54:00013 November 2003 14:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auto Start and Loading of the "B" Emergency Diesel Generator ENS 402482003-10-15T14:24:00015 October 2003 14:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Manual Reactor Trip from 1% Power as Per Abnormal Operating Procedures Occurred 2023-09-09T15:43:00 | |
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