View source for L-12-274, Steam Generator Tube Circumferential Crack Report - Spring 2012 Refueling Outage

{{Adams
| number = ML12234A484
| issue date = 08/20/2012
| title = Steam Generator Tube Circumferential Crack Report - Spring 2012 Refueling Outage
| author name = Allen B
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name = 
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000346
| license number = NPF-003
| contact person = 
| case reference number = L-12-274
| document type = Letter type:L
| page count = 1
}}

=Text=
{{#Wiki_filter:FENOC " RrstEnergy Nuclear Operating Company Bany S. Allen Vice President 
-Nuclear August 20, 2012 L-12-274 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

==SUBJECT:==
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 5501 North State Route 2 Oak Harbor. Ohio 43449 419-321-7676 Fax: 419-321-7582 Steam Generator Tube Circumferential Crack Report -Spring 2012 Refueling Outage In accordance with Davis-Besse Nuclear Power Station (DBNPS) License Condition 2.C(7), "Steam Generator Tube Circumferential Crack Report," FirstEnergy Nuclear Operating Company (FENOC) notified the Nuclear Regulatory Commission (NRC) of the steam generator tube inspections completed during DBNPS's spring 2012 refueling outage. This notification occurred during a May 23, 2012 teleconference.
On May 30,2012, the NRC was provided with updated steam generator tube inspection results via electronic mail. As requiredby License Condition 2.C(7), FENOC shall also demonstrate by evaluation that the primary-to-secondary leakage following a large break loss-of-coolant accident (LBLOCA), if any, continues to be acceptable when considering steam generator as-found conditions.
As reported to the NRC on May 30,2012, the best estimate LBLOCA leak rate is 0.0 gallons per minute (gpm) for steam generator 1-B, and 0.1133 gpm for steam generator 2-A. The combined estimated leak rate of 0.1133 gpm is less than the leak rate assumed during a LBLOCA. Therefore, it is bounded by current analyses, does not result in a significant increase of radionuclide release in excess of 10 CFR 100 limits, and demonstrates that adequate margin and defense-in-depth continue to be maintained.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor 
-Fleet Licensing, at (330) 315-6808.
Sincerely, A-&-Barry S. Allen cc: NRC Region III Administrator" NRC Resident Inspector . NRC Project Manager Utility Radiological Safety Board}}