ENS 41109
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ENS Event | |
|---|---|
22:14 Oct 10, 2004 | |
| Title | Manual Reactor Scram Due to a Steam Leak in the Turbine Building |
| Event Description | At 1814 [hrs. EDT] on October 10, 2004, Hope Creek Generating Station was manually scrammed due to a steam leak in the Turbine Building. All Control Rods inserted fully. Subsequent to the manual actuation of the Reactor Protection System, reactor pressure was reduced to minimize the effects of the steam leak. Degrading Main Condenser Vacuum following the scram resulted in trips of all operating Reactor Feed Pump Turbines at 10 [inches] HgA. The High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems were manually initiated for reactor level control and the Main Steam Isolation Valves (MSIV's) were closed to isolate the leak - MSIV closure was completed prior to reaching the Main Condenser Vacuum isolation setpoint of 21.5 [inches] HgA. During plant stabilization, Reactor Water Level lowered below the RPS actuation setpoint of 12.5 inches four separate times. First, following the initial scram. Second, immediately following initiation of the HPCI and RCIC systems, when the 'A' and 'B' Reactor Water Level channels lowered to -38 inches (Level 2). Level 2 is the HPCI and RCIC actuation setpoint and Primary Containment Isolation actuation setpoint for Groups 2, 7, 8, 9, 12, 13, 14, 17, 18, 19, and 20 valves. Because only two of the four Level 2 instrument channels actuated, the isolation of these systems was channel dependent and occurred as required by the respective isolation logic. Third, following manual closure of the MSIVs. Finally, Reactor Water Level lowered below 12.5 inches following reset of the original manual scram signal which resulted in an automatic scram signal. RCIC was re-initiated manually to restore Reactor Water Level.
No personnel were injured during this event. The plant is currently stable in OPCON 3 with reactor pressure at 615 psig. Pressure control (decay heat removal) was transitioned to HPCI in pressure control mode during plant stabilization. Reactor Water Level is being maintained with the Secondary Condensate Pumps. Two loops of RHR in Suppression Pool Cooling mode are in service with Suppression Pool Temperature at 110 degrees F in compliance with Technical Specification 3.6.2.1 Action b.2. Actions to determine the cause of the steam leak and effect repairs are in progress. The licensee will inform Lower Alloway Creek Township and has informed the NRC resident inspector.
On steam leak investigation, a walk down of the turbine building condenser bay determined the source of the leak to be a failure of an 8 inch moisture separator dump line. The line break is located approximately one foot from the condenser shell penetration. An additional investigation into the root cause of the failure has commenced. The NRC Resident Inspector was notified and Lower Alloway Creek Township will be notified. The Reg 1 RDO (Richard Barkley) and EO (Chris Grimes) were informed. HOO Note: See Event # 41110 |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.43 h-0.0179 days <br />-0.00256 weeks <br />-5.89014e-4 months <br />) | |
| Opened: | Bill Kopchick 21:48 Oct 10, 2004 |
| NRC Officer: | Mike Ripley |
| Last Updated: | Oct 11, 2004 |
| 41109 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (69 %) |
| After | Hot Shutdown (0 %) |
Hope Creek with 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)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 568892023-12-15T00:39:00015 December 2023 00:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 541982019-08-03T23:47:0003 August 2019 23:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Manual Actuation of Reactor Core Isolation Cooling ENS 523472016-11-05T08:04:0005 November 2016 08:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Rps While Reactor Shutdown ENS 514302015-09-29T00:46:00029 September 2015 00:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Following Trip of Both Reactor Recirculation Pumps ENS 496082013-12-05T08:25:0005 December 2013 08:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Following Turbine Trip on High Moisture Separator Level ENS 495922013-12-01T11:13:0001 December 2013 11:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 491082013-06-12T17:33:00012 June 2013 17:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Circulating Water Pump Trip Leads to Reactor Scram ENS 450742009-05-17T07:35:00017 May 2009 07:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Scram Air Header ENS 450162009-04-23T13:10:00023 April 2009 13:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Auto Load Sequencer During Fast Bus Transfer Testing ENS 437532007-10-29T02:03:00029 October 2007 02:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Refuel Floor Exhaust Hi-Hi Radiation Alarms During Reactor Reassembly ENS 433952007-05-29T12:35:00029 May 2007 12:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to Loss of Feed Pumps After Electrical Transient ENS 431322007-01-30T04:10:00030 January 2007 04:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Low Reactor Pressure Vessel (Rpv) Water Level ENS 411102004-10-11T01:53:00011 October 2004 01:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Rps Actuation Signal Occurred Due to Low Reactor Water Level While in Mode 3 ENS 411092004-10-10T22:14:00010 October 2004 22:14:00 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)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to a Steam Leak in the Turbine Building ENS 410942004-10-05T17:34:0005 October 2004 17:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Undervoltage Condition Initated Diesel Load Sequencer, Etc. Diesel Did Not Start. ENS 404372004-01-12T15:48:00012 January 2004 15:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Following Invalid Containment Isolation Signal ENS 403782003-12-06T04:49:0006 December 2003 04:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation a Level 3 Low Reactor Water Level Was Reached During a Reactor Water Level Transient ENS 402242003-10-04T21:13:0004 October 2003 21:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation While Critical 2023-12-15T00:39:00 | |
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