ENS 47874
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ENS Event | |
|---|---|
14:18 Apr 30, 2012 | |
| Title | Unusual Event Due to a Potential Fire in Containment |
| Event Description | Performing an I&C functional [test] caused an inadvertent Safety Injection signal resulting in a reactor trip/safety injection. All safety systems responded as designed for a safety injection. Electrical systems are aligned to normal offsite power sources. All fire alarms have been validated by the Fire Protection Department as invalid alarms and confirmed that no fire event in the protected area.
The reactor trip was successful and all rods [fully] inserted. Decay heat removal is via auxiliary feedwater through the atmospheric [steam] dumps. Unknown at this time is the cause of the inadvertent safety injection signal. No injuries occurred as a result of this event. The licensee believes that the trip/safety injection may have caused piping to shake resulting in dust near the fire detection equipment resulting in the invalid fire indication. The instrument being tested was the high steam flow channel-1 bistable for PT505. The maximum pressurizer level during this event was 95%. The licensee notified the NRC Resident Inspector.
At 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br /> on April 30, 2012, Salem Unit 1 experienced a reactor trip and safety injection (SI) signal due to a high steam flow coincident with a low steam pressure signal. At the time of the safety injection signal, function testing of the 1PT505 turbine inlet pressure channel was in progress. This testing required the tripping of the high steam flow bistables. As a result of the reactor trip and safety injection signal, the Emergency Diesel Generators started but did not load, the ECCS system (high head safety injection pumps actuated and injected into the reactor vessel, intermediate head safety injection pumps and low head (RHR) safety injection pumps) actuated. All 4 main steam isolation valves closed along with feedwater isolation and start of the auxiliary feedwater pumps. All control rods fully inserted following the reactor trip. Following the main steam line isolation, the atmospheric relief valves opened along with the lifting of several main steam safety valves. The unit is currently in Mode 3 and will be cooling down to Mode 4. Train A SSPS [Solid State Protection System] is currently out of service and suspected of causing the safety injection signal. Train B SSPS has not been reset due to the standing safety injection signal. With Train A SSPS inoperable and Train B SSPS not reset, TS 3.0.3 was entered and a shutdown required by TS 3.0.3 was commenced at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />. This report is being made in accordance with 10CFR50.72(b )(2)(iv)(B), 50.72(b)(3)(iv)(A), 50.72(b)(2)(i) and 50.72(b)(2)(iv)(A). The licensee exited the Unusual Event at 1249 EDT. The licensee notified the NRC Resident Inspector. Notified the R1DO (Conte). The NRC Operations Center notified other Federal Agencies (DHS SWO, FEMA Ops, DHS NICC, and NuclearSSA via e-mail). |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| Emergency class: | Unusual Event |
| 10 CFR 50.72(a) (1) (i), Emergency Class Declaration 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)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-3.55 h-0.148 days <br />-0.0211 weeks <br />-0.00486 months <br />) | |
| Opened: | Scott Riddell 10:45 Apr 30, 2012 |
| NRC Officer: | Charles Teal |
| Last Updated: | Apr 30, 2012 |
| 47874 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Salem with 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)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 562862022-12-24T07:22:00024 December 2022 07:22:00
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ECCS Discharge Unusual Event Due to a Potential Fire in Containment ENS 477662012-03-23T18:28:00023 March 2012 18:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Followed by Automatic Reactor Trip ENS 471912011-08-23T18:00:00023 August 2011 18:00:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Notification of an Unusual Event Due to a Seismic Event ENS 470522011-07-15T00:53:00015 July 2011 00:53:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Unusual Event Declared Based on Reactor Coolant Leak Greater than 10 Gpm ENS 469922011-06-26T04:00:00026 June 2011 04:00:00 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 Reactor Coolant Pump ENS 467742011-04-21T20:01:00021 April 2011 20:01:00 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 Circulating Water Pumps Out of Service ENS 463372010-10-17T09:12:00017 October 2010 09:12:00 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 4 Kv Group Bus Undervoltage Condition ENS 463362010-10-16T03:21:00016 October 2010 03:21:00 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 Turbine Trip ENS 460752010-07-07T15:17:0007 July 2010 15:17:00 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 Main Generator and Turbine Trip ENS 456472010-01-21T23:20:00021 January 2010 23:20:00 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 Low Steam Generator Water Level ENS 456042010-01-03T13:04:0003 January 2010 13:04:00 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 Loss of Circulators After Uptake of River Ice ENS 442052008-05-12T19:00:00012 May 2008 19:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shut Down Initiated Due to Inoperable Steam Generator Flow Channels ENS 438732007-12-28T22:54:00028 December 2007 22:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip on Failure of Station Power Transformer ENS 435502007-08-06T17:10:0006 August 2007 17:10:00 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 Spurious Interlock Signal to Feedwater Regulating Valves ENS 433822007-05-24T06:32:00024 May 2007 06:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 433292007-04-30T19:02:00030 April 2007 19:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Grass Intrusion Into Circulating Water Intake Structure ENS 433172007-04-25T02:48:00025 April 2007 02:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Circulators ENS 428642006-09-26T19:13:00026 September 2006 19:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Reactor Coolant Pump Seal Leakage. ENS 423952006-03-08T16:09:0008 March 2006 16:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip as a Result of a Turbine Generator Trip ENS 416702005-05-06T03:05:0006 May 2005 03:05:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Plant Shutdown Began and Then Terminated ENS 416162005-04-20T01:52:00020 April 2005 01:52:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specificiation Required Shutdown Related to Pressure Boundary Leakage ENS 415182005-03-24T12:42:00024 March 2005 12:42:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Loss of Control Room Annunciators ENS 410282004-09-09T05:06:0009 September 2004 05:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Turbine Trip/Reactor Trip ENS 408752004-07-15T23:44:00015 July 2004 23:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip from 8% Power Due to Lowering Water Level on 23 Steam Generator ENS 408652004-07-13T17:05:00013 July 2004 17:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Low Steam Generator Water Level. ENS 408232004-06-17T04:22:00017 June 2004 04:22:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Plant Shutdown Due to Emergency Core Cooling System Inoperable ENS 407872004-06-02T16:30:0002 June 2004 16:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Was Initiated to Comply with Tech Spec. 3.6.1.1. Primary Containment Integrity. ENS 407642004-05-21T17:15:00021 May 2004 17:15:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown ENS 403502003-11-23T10:19:00023 November 2003 10:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Was Manually Tripped After a Control Rod Dropped During Low Power Physics ENS 402502003-10-15T20:03:00015 October 2003 20:03:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Feedwater Regulating Valve Issue Forces Initiation of Technical Specification Shutdown ENS 397132003-03-29T09:42:00029 March 2003 09:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation 2022-12-24T07:22:00 | |
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