ENS 41453
ENS Event | |
|---|---|
20:45 Mar 1, 2005 | |
| Title | Manual Reactor Trip During a Rapid Shutdown for Steam Leak Repair |
| Event Description | The following information was provided by the licensee via facsimile (licensee text in quotes):
[The licensee] reduced power on Unit 2 due to a steam leak on a moisture separator reheater vent line. The reactor was manually tripped at 20% reactor power per normal shutdown sequence. All systems and components operated correctly. Unit restart will commence following completion of a planned refueling outage. All rods fully inserted. One steam line secondary PORV lifted and reseated. Decay heat removal is via AFW and steam bypass valves to the main condenser. The steam leak was reported to be on a 2-inch MSR vent line elbow. The licensee has notified the NRC Resident Inspector.
The following information was obtained from the licensee via facsimile (licensee text in quotes): On March 1, 2005, McGuire Unit 2 experienced a steam leak on a two-inch pipe in the heater bleed steam system. In consideration of that leak, Unit 2 was shutdown by manually tripping the reactor. This was reported as an unplanned valid actuation of the reactor protection system [10CFR 50.72 (b) (2)(iv)(B)]. Reference Event Report 41453. The manual reactor trip of Unit 2 was not required to mitigate the steam leak. However, in consideration of the steam leak, a decision was made to perform a shutdown of Unit 2 using the normal reactor shutdown procedure. This procedure requires that the control rods be inserted by manually tripping the reactor. As per guidance provided in NUREG-1022, the above actions do not satisfy the criteria for reporting under the requirements of 10CFR 50.72 (b) (2)(iv)(B) or any other reporting criteria. Therefore, McGuire is retracting Event Report 41453. The licensee has notified the NRC Resident Inspector. Notified R2DO (Cahill). |
| Where | |
|---|---|
Mcguire  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-4.43 h-0.185 days <br />-0.0264 weeks <br />-0.00607 months <br />) | |
| Opened: | Al Yoder 16:19 Mar 1, 2005 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Mar 17, 2005 |
| 41453 - 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 41453\u003C/a\u003E - \u003Ca href=\"/McGuire\" title=\"McGuire\"\u003EMcGuire\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EManual Reactor Trip During a Rapid Shutdown for Steam Leak Repair\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 41453 - McGuire\n","link":"","lat":35.43065277777778,"lon":-80.9415,"icon":"/w/images/7/75/Duke_Energy_icon.png"}],"imageoverlays":null} | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (20 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 557482022-02-18T09:59:00018 February 2022 09:59:00
[Table view]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 System Actuation ENS 540472019-05-03T19:54:0003 May 2019 19:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Over Temperature Delta Temperature ENS 532172018-02-16T15:14:00016 February 2018 15:14:00 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 Solid State Protection System Testing ENS 495382013-11-14T18:13:00014 November 2013 18:13:00 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 Indication of Dropped Control Rods ENS 487752013-02-21T14:57:00021 February 2013 14:57:00 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 on Loss of Both Main Feed Pumps ENS 465592011-01-20T20:18:00020 January 2011 20:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Both Main Feed Pumps During Shutdown ENS 460032010-06-12T10:44:00012 June 2010 10:44:00 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 Control Rod Drop Indication ENS 443182008-06-26T21:32:00026 June 2008 21:32:00 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 Loss of 1B Reactor Coolant Pump ENS 422112005-12-17T08:11:00017 December 2005 08:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from Full Power Due to a Failed Feed Flow Channel ENS 414532005-03-01T20:45:0001 March 2005 20:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During a Rapid Shutdown for Steam Leak Repair 2022-02-18T09:59:00 | |