ENS 40515
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ENS Event | |
|---|---|
04:58 Feb 12, 2004 | |
| Title | Eccs Actuation During Rcs Heatup |
| Event Description | At 2258 (CST) on 02/11/04, Callaway Plant was performing a heat up of the Reactor Coolant System in Mode 3 using plant procedure, OTG-ZZ-00001. When performing Section 6.4 of OTG-ZZ-00001, a Steam Line Pressure Safety Injection was initiated due to the automatic resetting of permissive P-11 at 1970 psig Reactor Coolant System pressure with steam line press less than 615 psig. Actual steam pressure was approximately 600 psig, 15 psig below the Steam Line Pressure Safety Injection set point. As a result of the Safety Injection [signal], the following safety related systems actuated: Safety Injection, Residual Heat Removal, Auxiliary Feedwater, Essential Service Water, and both of the Emergency Diesel Generators. During the injection phase, Pressurizer water level increased to approximately 98 percent and pressurizer pressure increased above the Pressurizer Power Operated Relief Valve (PORV) set point causing the PORVs to operate. During the operation of the PORVs, an open alarm for a Pressurizer Safety Relief Valve actuated, however, there are no indications that this valve actually opened. Initial indications are that a valve position limit switch has malfunctioned.
All systems responded as expected during the event with the exception of the above mention Pressurizer Safety valve position indication problem and one Steam Generator Atmospheric Safety Valve that would not operate properly in Manual. At present, the plant is being stabilized using plant procedures. Both Emergency Diesel Generators are in standby and the primary system is at 500 degrees F and 1900 psig with Pressurizer level at 25%. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Callaway  Missouri (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000483/LER-2004-004 |
| Time - Person (Reporting Time:+-1.12 h-0.0467 days <br />-0.00667 weeks <br />-0.00153 months <br />) | |
| Opened: | Jim Milligan 03:51 Feb 12, 2004 |
| NRC Officer: | Bill Gott |
| Last Updated: | Feb 12, 2004 |
| 40515 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
Callaway with 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 569682024-02-15T08:47:00015 February 2024 08:47:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip/Reactor Trip ENS 556982022-01-07T18:23:0007 January 2022 18:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip / Reactor Trip ENS 540692019-05-17T04:03:00017 May 2019 04:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation En Revision Imported Date 6/6/2019 ENS 540052019-04-17T06:37:00017 April 2019 06:37:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Undervoltage to a Safety Related Bus Resulting in Valid System Actuation ENS 518462016-04-03T04:02:0003 April 2016 04:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Protection System Actuation While Reactor Shutdown ENS 513082015-08-11T06:39:00011 August 2015 06:39:00 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 an Offsite Electrical Fault ENS 512572015-07-23T18:57:00023 July 2015 18:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Manual Start Due to Loss of Main Feedwater Pump During Plant Cooldown ENS 506502014-12-03T06:22:0003 December 2014 06:22:00 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 Turbine Trip ENS 492192013-07-27T04:49:00027 July 2013 04:49:00 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 a Fire in the Turbine Building Lasting Greater than 15 Minutes ENS 457152010-02-20T03:45:00020 February 2010 03:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuations Due to Loss of the 'A' Safeguards Transformer ENS 447192008-12-14T23:14:00014 December 2008 23:14:00 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 Electrical Fault on an Operating Condensate Pump ENS 447172008-12-12T16:42:00012 December 2008 16:42:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Valid Reactor Trip and Feedwater Isolation Signals Due to Maintenance ENS 447142008-12-12T05:01:00012 December 2008 05:01:00 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 Transient ENS 446522008-11-12T00:46:00012 November 2008 00:46:00 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 Feedpump Trip ENS 445612008-10-11T10:08:00011 October 2008 10:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Steam Generator Water Level Trip Actuation Initiated Reactor Trip System ENS 432272007-03-09T16:43:0009 March 2007 16:43:00 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(b)(3)(iv)(A), System Actuation Manual Reactor Trip at Reduced Power Due to Inadequate Feedwater Control ENS 426212006-06-06T18:39:0006 June 2006 18:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of "a" Train of Offsite Vital Power Due to Relay Testing ENS 425712006-05-12T05:53:00012 May 2006 05:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on High Steam Generator Level ENS 415462005-03-29T16:57:00029 March 2005 16:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of the Reactor Protection System and Auxiliary Feedwater System While Establishing Initial Conditions for Leak Test in Mode 3. ENS 413472005-01-19T18:51:00019 January 2005 18:51:00 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(b)(3)(iv)(A), System Actuation Callaway Automatic Reactor Trip on Low Steam Generator Level ENS 405222004-02-15T21:19:00015 February 2004 21:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip with Auxiliary Feedwater Actuation ENS 405152004-02-12T04:58:00012 February 2004 04:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Eccs Actuation During Rcs Heatup ENS 405002004-02-03T10:39:0003 February 2004 10:39:00 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 Genrator Output Breakers Opening. ENS 403172003-11-12T20:21:00012 November 2003 20:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Actuation of Essential Service Water System 2024-02-15T08:47:00 | |
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