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

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: L-14-241, Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4 ML14224A575 ML14224A576 ML14224A577
References
L-14-241
Download: ML14224A574 (1)

Text

FENOCTM Beaver Valley Power Station P.O. Box4 FirstEnergy Nuclear Operating Company Shmomaoo~PA 15077 Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 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 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.

Sincerely~

~V.//JJ~

!(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