ENS 47052
ENS Event | |
|---|---|
00:53 Jul 15, 2011 | |
| Title | Unusual Event Declared Based On Reactor Coolant Leak Greater Than 10 Gpm |
| Event Description | At 2053 on July 14, 2011 Salem unit 2 declared an Unusual Event due to reactor coolant system leakage greater than 10 gallons per minute. While performing a monthly Emergency Core Cooling System vent of the high head safety injection piping a motor operated valve was opened and a leak developed on the high head piping greater than 10 gallons per minute. The leak rate was approximately 11-15 gallon per minute. The leak was terminated when the motor operated valve was closed. The time of the leak was about 6 minutes.
At this time the leak is believed to be from a crack on the Boron Injection Tank (BIT) relief valve line which is connected to the high head piping. A total of approximately 90 gallon of reactor coolant leaked into the BIT room. The licensee has declared the high head safety injection inoperable and is proceeding to shutdown under Tech Spec 3.0.3. The license has notified appropriate State and local authorities. The licensee will notify the NRC Resident Inspector.
Salem Unit 2 declared an Unusual Event due to Reactor Coolant System (RCS) leakage being greater than 10 gpm and pressurizer level decreasing. Leakage was estimated to be approximately 15 gpm. The leakage was determined to be from a weld on the high head charging injection relief valve connection. This leaking weld impacts both trains of high head charging/safety injection. Both trains of high head charging/safety injection were declared inoperable at 2038 [EDT] on July 14, 2011, entering TS 3.0.3. Salem Unit 2 began the Technical Specification shutdown in accordance with TS 3.0.3 at 2136 [EDT]. The technical specification shutdown is being reported in accordance with 10CFR50.72(b)(2)(i) and RAL 11.1.1.a. In addition since the leakage from the weld on the high head charging/safety injection piping exceeded the analyzed limit for ESF leakage outside containment, this event is also being reported in accordance with 10CFR50.72(b)(3)(v) and RAL 11.2.2.b as a condition that prevents the ability to mitigate the consequences of an accident. Salem unit 2 is currently at 27% and reducing power. The licensee notified the states of New Jersey and Delaware, Lower Alloways Creek Township and the NRC Resident Inspector. Notified the R1DO (Dwyer), NRR-EO (Giiter) and IRD (Morris).
Salem Unit 2 has exited the Unusual Event as of 0339 EDT. The criteria for exit was the leakage rate was below the 10 gpm rate. The plant is in Mode 3 and is preparing to cooldown. The licensee will notify the NRC Resident Inspector. Notified the R1DO (Dwyer), NRR EO (Giitter), IRD (Morris), DHS(Hill), and FEMA (Blankenship). |
| 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)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+-3.05 h-0.127 days <br />-0.0182 weeks <br />-0.00418 months <br />) | |
| Opened: | Karl Hanpho 21:50 Jul 14, 2011 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jul 15, 2011 |
| 47052 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 47052\u003C/a\u003E - \u003Ca href=\"/Salem\" title=\"Salem\"\u003ESalem\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EUnusual Event Declared Based on Reactor Coolant Leak Greater than 10 Gpm\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 47052 - Salem\n","link":"","lat":39.46302222222222,"lon":-75.53561388888889,"icon":"/w/images/c/cc/PSEG_icon.png"}],"imageoverlays":null} | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Salem with 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 | |
WEEKMONTHYEARENS 530992017-11-30T21:57:00030 November 2017 21:57:00
[Table view]10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Earthquake ENS 526992017-04-21T01:10:00021 April 2017 01:10:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Hydrazine in Containment ENS 525812017-02-28T15:00:00028 February 2017 15:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Reactor Coolant System Pressure Boundary Leakage ENS 521292016-07-28T09:41:00028 July 2016 09:41:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Source Range Instruments Reading Improperly During a Reactor Startup ENS 515632015-11-24T02:48:00024 November 2015 02:48:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Reactor Coolant System Leakage ENS 512222015-07-11T22:22:00011 July 2015 22:22:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event for a Co2 Release Affecting Normal Plant Operations ENS 511702015-06-22T18:06:00022 June 2015 18:06:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Sodium Hydroxide Below Technical Specification Required Concentration ENS 508962015-03-15T16:27:00015 March 2015 16:27:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Due to Failure to Restore Containment Fan Cooler Unit ENS 493002013-08-22T20:26:00022 August 2013 20:26:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit 1 Commenced a Ts Required Shutdown Due to Unidentified Rcs Leakage > 1 Gpm ENS 478742012-04-30T14:18:00030 April 2012 14:18:00 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)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Unusual Event Due to a Potential Fire in Containment 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 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 423432006-02-16T04:45:00016 February 2006 04:45:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Potential Uncontrolled Radiological Release ENS 421142005-11-03T15:30:0003 November 2005 15:30:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Eccs Leakage Outside Containment 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 412452004-12-05T15:15:0005 December 2004 15:15:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Reactor Coolant Leakage Outside of Containmemt 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 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 2017-04-21T01:10:00 | |