ENS 48585
ENS Event | |
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05:00 Dec 13, 2012 | |
Title | 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers |
Event Description | The following information was received via fax:
Summary GE Hitachi Nuclear Energy (GEH) is investigating the adequacy of a Design Change in AM 4.16-350-2C and AM 4.16-350-2H Magne-Blast Circuit Breakers as a result of a breaker failure at a BWR Licensee. GEH has not completed the evaluation of this condition to determine reportability under 10 CFR Part 21 and is therefore issuing this 60-day Interim Notification. GEH will close or issue an update on this matter on or before June 14, 2013. Given the early status of the evaluation, GEH has no recommended actions at this time. This 60-day Interim Notification is issued in accordance with 10 CFR Part 21.21(a)(2), and will be sent to all GE BWR/2-6 plants and all PWRs. Recommendation GEH advises licensees to take no action at this time. However, if licensees wish to determine if the extent of this issue is present at their respective plants, they may identify breaker models AM 4.16-350-2H/2C with a date of manufacture prior to October 6, 1971. Other AM breaker styles do not use the booster cylinder as designed in breaker model AM 4.16-350-2H/2C and are not included in this concern. Therefore the extent is limited to the AM 4.16-350-2H/2C models manufactured prior to October 6, 1971. US Plants Potentially Affected Nine Mile Point 1-2, Fermi 2, Columbia, Grand Gulf, River Bend, FitzPatrick, Pilgrim, Vermont Yankee, Clinton, Dresden 2-3, LaSalle 1-2, Limerick 1-2, Oyster Creek, Peach Bottom 2-3, Quad Cities 1-2, Perry 1, Duane Arnold, Cooper, Susquehanna 1-2, Brunswick 1-2, Hope Creek, Hatch 1 - 2, Browns Ferry 1-3, Monticello, Callaway, Palo Verde 1-3 , Calvert Cliffs 1-2, Ginna, Arkansas Nuclear One 1-2, Indian Point 2-3, Millstone 2, Millstone 3, North Anna 1-2, Palisades, Surry 1-2, Waterford 3, Catawba 1-2, Oconee 1-3, McGuire 1-2, Braidwood 1-2, Exelon Byron 1-2 , Three Mi le Island 1, Beaver Valley 1-2, Davis-Besse, Seabrook, St. Lucie 1-2, Turkey Point 3-4, Point Beach 1-2, DC Cook 1-2, Prairie Island 1-2, Fort Calhoun, Diablo Canyon 1-2, Crystal River 3, Robinson, Shearon Harris, Salem 1, Salem 2, Summer, South Texas Project 1-2, San Onofre 2-3, Farley 1-2, Vogtle 1-2, Sequoyah 1-2, Watts Bar 1, Comanche Peak 1-2, and Wolf Creek. If you have an questions, please call me at (910) 819-4491. Dale E. Porter Safety Evaluation Program Manager GE-Hitachi Nuclear Energy Americas LLC Hitachi Reference Number: MFN-128 R0
The following information was received via fax: [GE Hitachi Nuclear Energy] GEH has completed all testing and evaluations and has determined that the condition previously described in MFN 12-128 R0 is not a reportable condition under 10 CFR Part 21. This information will be sent to all GE BWR/2-6 plants and all PWRs that were previously notified under the 10CFR21.21(a)(2) communication. Notified R1DO (Dentel), R2DO (Ehrhardt), R3DO (Lara), R4DO (Gepford), and Part 21 Group via email. |
Where | |
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Ge Hitachi Nuclear Energy Wilmington, North Carolina (NRC Region 1) | |
Organization: | Ge Hitachi Nuclear Energy |
Reporting | |
10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component | |
Time - Person (Reporting Time:+3.68 h0.153 days <br />0.0219 weeks <br />0.00504 months <br />) | |
Opened: | Dale E. Porter 08:41 Dec 13, 2012 |
NRC Officer: | Steve Sandin |
Last Updated: | Jun 12, 2013 |
48585 - NRC Website | |
Ge Hitachi Nuclear Energy with 10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component | |
WEEKMONTHYEARENS 526922017-02-27T04:00:00027 February 2017 04:00:00
[Table view]10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ENS 485852012-12-13T05:00:00013 December 2012 05:00:00 10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ENS 483502012-09-27T15:01:00027 September 2012 15:01:00 10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component Error in Main Steam Line High Flow Calculational Methodology ENS 476302012-02-01T05:00:0001 February 2012 05:00:00 10 CFR 21.21(a)(2), Interim Report for Comply or Defect in Component Part 21 Report - Failure of Crd Collet Retainer Tube/Outer Tube Weld 2017-02-27T04:00:00 | |