ML12194A600
| ML12194A600 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/18/2012 |
| From: | Ellen Brown Plant Licensing Branch II |
| To: | James Shea Tennessee Valley Authority |
| Brown, Eva A. | |
| References | |
| TAC ME8854, 2-ISI-29 | |
| Download: ML12194A600 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-1)001 July 18, 2012 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REVIEW OF REQUESTED LICENSING ACTION CONCERNING RELIEF REQUEST 2-151-29 (TAC NO. ME8854)
Dear Mr. Shea:
By letter dated May 25,2012, the Tennessee Valley Authority (the licensee) submitted a relief request (RR) 2-151-29 for Browns Ferry Nuclear Plant Unit 2. The proposed RR if approved would allow the licensee to perform ultrasonic testing to the maximum extent practical for selected full penetration austentitic stainless and dissimilar metal piping welds. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Title 10 of the Code of Federal Regulations (10 CR), Section 50.55a(g)(5)(iii), the licensee had until May 24, 2012 to notify the NRC of the inability to meet the ASME Code requirements for these examinations which were completed in the third 1 O-year inspection cycle (May 25,2001 to May 24,2011). On May 29,2012, it was determined that the licensee had not requested relief for the weld examinations by the 12 month cutoff date of May 24,2012.
Because of the failure to request relief consistent with the 10 CFR 50.55a requirements, the NRC staff's review will be limited to a determination of the adequacy of the achieved coverage as it relates to the functionality and structural integrity of the affected piping and associated systems. The NRC staff will be in contact should additional information be needed to support this review.
J. Shea
- 2 If you have any questions, please feel free to contact me at (301) 415-2315.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260 cc: Distribution via Listserv
ML12194A600 OFFICE LPLlI-2/PM
~1-2/LA DORULPLlI-2/BC(A)
NAME EBrown BClayton JQuichocho DATE 07/18/12 107/13/12 07/18/12