ML14309A529
| ML14309A529 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/31/2014 |
| From: | Polson K Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML14309A529 (2) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 October 31, 2014 10 CFR 21.21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc. -
Emergency Diesel Generator Heat Exchanger CEY564L-HEX
Reference:
Letter from TVA to NRC, "10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX," dated September 5, 2014 In the reference letter dated September 5, 2014, the Tennessee Valley Authority (TVA) notified the Nuclear Regulatory Commission (NRC) of a leak in the weld of the Emergency Equipment Cooling Water outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX. TVA's evaluation of this leak concluded that the condition had the potential to constitute a reportable condition pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," and as such, additional analysis was required in order to determine the significance of the weld defect. The referenced letter stated the final 10 CFR Part 21 report would be submitted to the NRC by November 6, 2014.
Structural Integrity Associates, Inc. was contracted to perform an evaluation weld failure on the C2 EDG heat exchanger. This evaluation concluded weld cracks would not propagate circumferentially any further; therefore, the heat exchanger would have continued to function and the EDG would have maintained Operability. Based on the results of this evaluation, this condition was determined not to be reportable in accordance with 10 CFR 21.21, and the referenced interim report may be closed with no additional actions required.
U.S. Nuclear Regulatory Commission Page 2 October 31, 2014 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, K.J son Vice President cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plan