CNL-20-079, Supplement to American Soc. of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47

Supplement to American Soc. of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47

ML20255A150
Person / Time
Site:	Browns Ferry
Issue date:	09/10/2020
From:	Jerrica Johnson Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-20-079, EPID L-2020-LLR-0034)
Download: ML20255A150 (2)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-079 September 10, 2020 10 CFR 50.55a 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:

Browns Ferry Nuclear Plant, Units 1, 2, and 3, Supplement to American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47 (EPID L-2020-LLR-0034)

References:

1. TVA Letter to NRC, CNL-20-019, Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47, dated February 28, 2020 (ML20059N637)

2. NRC Electronic Mail to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 (EPID L-2020-LLR-0034), dated July 13, 2020 (ML20195B130)

3. TVA Letter to NRC, CNL-20-059, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -- Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals (EPID L-2020-LLR-0034), dated August 10, 2020 (ML20223A366)

In Reference 1, Tennessee Valley Authority (TVA) submitted a request for an alternative in accordance with Title 10 of the Code of Federal Regulations, Part 50.55a, paragraph (z)(1), to use guidance from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Inspection and Evaluation Guidelines in lieu of certain requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code),Section XI, examination requirements for Examination Categories B-N-1 and B-N-2.

U.S. Nuclear Regulatory Commission CNL-20-079 Page 2 September 10, 2020 In Reference 2, the Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI) and in Reference 3, TVA responded to the RAIs. Specifically, the NRC stated in Reference 2 that the NRC staff is unable to approve TVAs proposal that revisions to BWRVIP guidelines appropriately screened in accordance with Nuclear Energy Institutes (NEI) 03-08 screening process be implemented by TVA without a subsequent plant-specific request to the NRC, because TVA was requesting to use revisions of BWRVIP Topical Reports that are not available for review by NRC staff. In Reference 3, TVA agreed to remove this proposal.

Subsequent to TVAs response, the NRC informed TVA that one of the BWRVIP Topical Reports (BWRVIP-48-R1) cited in Reference 1 had already been screened using the NEI 03-08 screening process, but was not available for NRC review. Thus, it could not be referenced in TVAs request for alternative.

Therefore, wherever BWRVIP-48-R1 is referenced within TVAs request for alternative, consider BWRVIP-48-R1 replaced with BWRVIP-48-A. Also, in regard to core spray bracket to vessel inner diameter attachment weld inspections, where the inspection interval is stated as every 10 years, consider the inspection interval to be stated as every four refueling outages as noted in BWRVIP-48-A.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Gordon Williams, Senior Manager Fleet Licensing (Acting) at 423-751-2687.

Respectfully, Jonathan T. Johnson Director, Nuclear Regulatory Affairs (Acting) cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant