L-14-241, Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4: Difference between revisions

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| issue date = 08/11/2014
| issue date = 08/11/2014
| title = Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4
| title = Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4
| author name = Larson E A
| author name = Larson E
| author affiliation = FirstEnergy Nuclear Operating Co
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =  
| addressee name =  

Revision as of 09:31, 21 June 2019

Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4
ML14224A574
Person / Time
Site: Beaver Valley
Issue date: 08/11/2014
From: Emily Larson
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML14224A573 List:
References
L-14-241
Download: ML14224A574 (1)


Text

FENOCTM FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President August 11, 2014 L-14-241 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Beaver Valley Power Station P.O. Box4 15077 724-682-5234 Fax: 724-643-8069 Steam Generator Inspection Reports-Technical Specifications 5.6.6.2.2 and 5.6.6.2.4 In accordance with Beaver Valley Power Station, Unit No.2 Technical Specifications 5.6.6.2.2 and 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits three reports containing steam generator inspection results. The enclosed reports provide information required by the technical specifications that was obtained during inspections conducted during the spring 2014 refueling outage. Remaining metallurgical examination results will be submitted when available.

There are no regulatory commitments contained in this submittal.

If there are any questions or if additional information is required, please contact Mr. Thomas A Lentz, Manager-Fleet Licensing, at (330) 315-6810.

!(jr-Eric A Larson

Enclosures:

A Beaver Valley Unit 2 End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report B. Unit #2-2R17 Steam Generator F* (F Star) Report C. Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative