NL-05-0518, Reactor Vessel Surveillance Capsule X Results and Unit 2 Reactor Vessel Surveillance Capsule W Results

From kanterella
(Redirected from ML050840317)
Jump to navigation Jump to search
Reactor Vessel Surveillance Capsule X Results and Unit 2 Reactor Vessel Surveillance Capsule W Results
ML050840317
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/21/2005
From: Grissette D
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-05-0518
Download: ML050840317 (2)


Text

Don E.Grissette Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 SOUTHERNNA COMPANY March 21, 2005 Energy to Serve Your World '

Docket Nos.: 50-424 NL-05-0518 50425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Unit I Reactor Vessel Surveillance Capsule X Results and Unit 2 Reactor Vessel Surveillance Capsule W Results Ladies and Gentlemen:

Pursuant to 10 CFR 50 Appendix H, Southern Nuclear Operating Company (SNC) hereby submits Westinghouse Report WCAP-16278-NP, Rev. 0, "Analysis of Capsule X from the Southern Nuclear Operating Company, Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program." Capsule X was withdrawn during the Vogtle Unit I fall 2003 maintenance/refueling outage; therefore, SNC failed to meet the 10 CFR 50 Appendix H, IV.A. requirement to submit the report within one year of the date of capsule withdrawal.

The NRC was informed at the time of discovery and the condition has been entered in the SNC Corrective Action Program.

The report (WCAP-16278, Rev. 0) presents the surveillance capsule test results from Capsule X, the 4th capsule removed from the Unit I reactor vessel. This report includes the data required by ASTM E 185-82, and the results of all fracture toughness tests conducted on the beltline materials. Based on the enclosed surveillance capsule test results, properties of the reactor beitline materials are predicted to remain more than adequate for continued safe plant operation through the end of the current license (about 36 EFPY) and a potential license renewal (to about 54 EFPY). The evaluation of the Vogtle Unit I Capsule X mechanical and fluence results determined that the Pressure Temperature Limits Report (PTLR) from WCAP-15068, Rev. 3 is still acceptable for 26 EFPY and 36 EFPY.

Additionally, in accordance with the provisions of 10 CFR 50 Appendix H, SNC hereby submits Westinghouse Report WCAP-16382-NP, Rev. 0, "Analysis of Capsule W from the Southern Nuclear Operating Company, Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program."

U. S. Nuclear Regulatory Commission NL-05-0518 Page 2 This report (WCAP-16382-NP, Rev. 0) presents the surveillance capsule test results from Capsule W, the 4th capsule removed from the Unit 2 reactor vessel. This report includes the data required by ASTM E 185-82, and the results of all fracture toughness tests conducted on the beltline materials. Based on the enclosed surveillance capsule test results, properties of the reactor beltline materials are predicted to remain more than adequate for continued safe plant operation through the end of the current license (about 36 EFPY) and a potential license renewal (to about 54 EFPY). The evaluation of the Vogtle Unit 2 Capsule W mechanical and fluence results determined that the PTLR from WCAP-15161, Rev. 3 is still acceptable for 26 EFPY and 36 EFPY.

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, Don E. Grissette DEG/DRG/daj

Enclosures:

1. WCAP-16278-NP, Rev. 0, "Analysis of Capsule X from the Southern Nuclear Operating Company, Vogtle Unit I Reactor Vessel Radiation Surveillance Program."
2. WCAP-16382-NP, Rev. 0, "Analysis of Capsule W from the Southern Nuclear Operating Company, Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program."

cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatorv Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager- Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle