ENS 42531
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ENS Event | |
|---|---|
06:07 Apr 27, 2006 | |
| Title | Low Pressure Steam Line Pressure Safety Injection Signal Inadvertently Initiated |
| Event Description | On 4/27/06 at 02:00, with D.C. Cook Unit 2 in Mode 5 and the Control Rod Drive System de-energized under clearance and incapable of withdrawal, Instrumentation and Controls Technicians were beginning Instrumentation Channel Operational Test and Trip Actuating Device Operational Tests. The block for Main Steam Line Low Pressure Safety Injection was inadvertently removed. This allowed the existing low steam generator pressure (0 psig) and low RCS temperature (186 degrees F) to initiate a Low Steam Line Pressure Safety Injection and a Steam Line Isolation signal.
At 02:07 Unit 2 had a Main Steam Line Low Pressure Safety Injection signal on both Trains. The following components automatically started: Unit 2 West Centrifugal Charging Pump (on minimum flow recirc path with injection path isolated for LTOP -- no injection to RCS) Unit 2 South Safety Injection Pump (on minimum flow recirc path with injection path isolated for LTOP - no injection to RCS) Unit 2 East Residual Heat Removal Pump Unit 2 East Component Cooling Water Pump Unit 2 CD Emergency Diesel Generator Both Trains of Unit 2 Control Room Pressurization Both Trains of Unit 2 Phase A Containment Isolation signal Both Trains of Unit 2 Containment Ventilation Isolation. Both Trains of Unit 1 Control Room Pressurization Fans Unit 1 West Essential Service Water Pump All available equipment actuated as expected for this condition. (The Unit 2 Boron Injection Tank was isolated under clearance for LTOP. The Unit 2 East Centrifugal Charging Pump, Unit 2 West Residual Heat Removal Pump, and Unit 2 West Component Cooling Water Pump were already running. The Unit 2 AB Emergency Diesel Generator was under a clearance for maintenance. The Unit 2 North Safety Injection Pump was under an administrative clearance for LTOP. The Unit 1 East Essential Service Water Pump was already running.) After diagnosing the event, operators manually blocked the Steam Line Isolation and manually reset Safety Injection signals for both trains. Components were returned to normal status for plant conditions. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Cook  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+3.18 h0.133 days <br />0.0189 weeks <br />0.00436 months <br />) | |
| Opened: | Dale Turinetti 09:18 Apr 27, 2006 |
| NRC Officer: | John Knoke |
| Last Updated: | Apr 27, 2006 |
| 42531 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 562162022-11-10T12:44:00010 November 2022 12:44:00
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Level in Moisture Separator Drain Tank ENS 533342018-04-13T19:55:00013 April 2018 19:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Emergency Diesel Generator Start During Testing ENS 520652016-07-06T04:38:0006 July 2016 04:38:00 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 Manual Reactor Trip and Unusual Event Declaration Due to Steam Leak in Turbine Building ENS 510042015-04-23T06:10:00023 April 2015 06:10:00 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)(2)(i), Tech Spec Required Shutdown Manual Reactor Trip Due to a Secondary Plant Transient ENS 505872014-11-01T06:48:0001 November 2014 06:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Dual Unit Manual Reactor Trips Due to Lowering Condenser Vacuum and Degraded Forebay ENS 492202013-07-28T14:18:00028 July 2013 14:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Secondary Plant Transient ENS 489642013-04-24T18:11:00024 April 2013 18:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of an Emergency Diesel Generator Due to a Loss of Train a Reserve Feed to the Site ENS 478812012-05-01T03:28:0001 May 2012 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 Main Turbine Trip ENS 474772011-11-25T10:23:00025 November 2011 10:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Aux Feedwater Pump Start After Main Feedwater Pump Trip ENS 472472011-09-07T12:54:0007 September 2011 12:54:00 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 Turbine Trip from 100% Power ENS 464772010-12-14T02:19:00014 December 2010 02:19:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Auxiliary Feedwater System in Response to Loss of One Main Feedwater Pump ENS 463112010-10-06T04:08:0006 October 2010 04:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Auxiliary Feedwater System in Response to Valid Steam Generator Low-Low Level Signals ENS 458932010-05-02T12:58:0002 May 2010 12:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Auxiliary Feedwater System in Response to Loss of One Main Feedwater Pump ENS 452282009-07-26T19:06:00026 July 2009 19:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to a Reactor Coolant Pump Seal Malfunction ENS 445072008-09-21T00:18:00021 September 2008 00:18:00 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 Unit 1 Manual Reactor Trip from 100% Power Due to a Fire in the Main Turbine ENS 439562008-02-02T10:30:0002 February 2008 10:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to High Turbine Vibrations ENS 436052007-08-28T17:54:00028 August 2007 17:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip After Digital Feedwater System Failure ENS 425312006-04-27T06:07:00027 April 2006 06:07:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Low Pressure Steam Line Pressure Safety Injection Signal Inadvertently Initiated ENS 421252005-11-08T08:58:0008 November 2005 08:58:00 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 Reactor Coolant Pump Bus Undervoltage ENS 416392005-04-26T04:02:00026 April 2005 04:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip with Afw Actuation ENS 406602004-04-09T02:16:0009 April 2004 02:16:00 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 Feedwater Flow Transient ENS 406222004-03-29T19:04:00029 March 2004 19:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Reactor Trip Bypass Breaker Manipulation Test ENS 404192003-12-30T18:30:00030 December 2003 18:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Tripped from 100% Power Due to Low Steam Generator 2022-08-28T17:48:00 | |
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