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

{{Adams
| number = ML14224A574
| 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
| author name = Larson E
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000412
| license number = NPF-073
| contact person = 
| case reference number = L-14-241
| package number = ML14224A573
| document type = Letter type:L
| page count = 1
}}

=Text=
{{#Wiki_filter: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}}