ML061640113

License Condition 2.C(7) Report for the Fourteenth Refueling Outage Steam Generator Tube (Circumferential Cracking) Inspection

ML061640113
Person / Time
Site:	Davis Besse
Issue date:	06/09/2006
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3260
Download: ML061640113 (3)

Text

FENOC 10-4%5501 North State Route 2 First~negy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bzla419-321-7676 Vice President

-Nuclear Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 3260 June 9, 2006 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001

Subject:

Davis-Besse Nuclear Power Station License Condition 2.C(7) Report for the Fourteenth Refueling Outage Steam Generator Tube (Circumferential Cracking)

Inspection Ladies and Gentlemen:

This letter is submitted in accordance with the requirements of the Operating License for the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1. License Condition 2.C(7)requires the FirstEnergy Nuclear Operating Company (FENOC) to report to the Nuclear Regulatory Commission (NRC) information related to specific indications identified during inservice inspection of steam generator tubes. This letter satisfies License Condition 2.C(7) in its entirety for the inspections performed during the recent fourteenth refueling outage (I 4RFO). No supplemental report will be provided.

The information specified by the license condition is provided below: a. No License Condition 2.C(7) indications were found inboard of any installed repair roll.b. There were two tubes in Steam Generator (SG) 2A and one tube in SG IlB which had new circumferential Primary Water Stress Corrosion Cracking (PWSCC) crack indications in the tube-to-tubesheet seal weld heat affected zone. Also in SG 1 B, one circumferential PWSCC indication was discovered at the heel of a shop re-roll in the lower tube sheet. These four tubes were repaired in accordance with Technical Specification 4.4.5.4 requirements.

These indications met the reporting requirements of License Condition 2.C(7).c. Based on the License Condition 2.C(7) indications identified, the evaluation has determined that no leakage from any such indication in the original tube-to-tubesheet rolls, tube-to-tubesheet re-roll repairs, and heat affected zones of seal welds would have been expected following a large-break loss-of-coolant accident (LBLOCA).

The LBLOCA Leakage AooI Docket Number 50-346 License Number NPF-3 Serial Number 3260 Page 2 Integrity Evaluation was included in the DBNPS 14RFO Steam Generator Condition Monitoring and Operational Assessment Evaluation.

The best-estimate primary-to-secondary leakage following a LBLOCA has been determined to be 0.00 gpm. Accordingly, the off-site dose consequences from a LBLOCA would be below 10 CFR Part 100 limits.Attachment 1, Commitment List, identifies that there are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at (330) 315-7243.Very truly yours, TSC Attachment I cc: Regional Administrator, NRC Region III NRC/NRR Project Manager NRC Senior Resident Inspector Utility Radiological Safety Board Docket Number 50-346 License Number NPF-3 Serial Number 3260 Attachment I COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMFITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT.

ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATORY COMMITMENTS.

IF THERE ARE ANY QUESTIONS OR IF ADDITIONAL INFORMATION IS REQUIRED, PLEASE CONTACT MR. GREGORY A. DUNN, MANAGER -FENOC FLEET LICENSING, AT (330) 315-7243.Commitment Due Date NoneNA N/A