View source for CNL-18-129, Correction to Request for Additional Information (RAI) Response and License Amendment 305, 328, and 288 Safety Evaluation

{{Adams
| number = ML18334A358
| issue date = 11/29/2018
| title = Correction to Request for Additional Information (RAI) Response and License Amendment 305, 328, and 288 Safety Evaluation
| author name = Henderson E
| author affiliation = Tennessee Valley Authority
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| contact person = 
| case reference number = CNL-18-129
| document type = Letter type:CNL
| page count = 2
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-129 November 29, 2018 10 CFR 50.4 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 No. 50-259, 50-260, and 50-296

==Subject:==
Correction to Request for Additional Information (RAI) Response and License Amendment 305, 328, and 288 Safety Evaluation

==References:==
: 1. TVA letter to NRC, CNL-18-011,Tennessee Valley Authority Response to NRC Request for Additional Information related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing, dated February 5, 2018 (ML18036A901)
: 2. NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292), dated September 27, 2018 (ML18251A003)
The purpose of this letter is to notify you of a typographical error discovered in the referenced documents during the course of an internal self-assessment. In Reference 1, in response to RAI SCPB RAI-2c, Tennessee Valley Authority (TVA) made the following statement:
3-FCV-77-2B has an Administrative limit of 6 scfh. The RF16 as-found test result was 10.85 scfh. The valve was disassembled, cleaned and inspected. The RF16 as-left result was 1.91 scfh [emphasis added].
Based on that information, Reference 2 reiterated that the BNF Unit 3 Refueling Outage 16 post-maintenance test as-left result for 3-FCV-77-2B was 1.91 standard cubic feet per hour (scfh). In fact, review of the as-left testing records showed a lesser leakage rate of 1.61 scfh.

U.S. Nuclear Regulatory Commission CNL-18-129 Page 2 November 29, 2018 This issue has been entered into the TVA Corrective Action Program, and the Nuclear Regulatory Commission (NRC) Project Manager for the Browns Ferry Units was notified. TVA's assessment is that the error had no impact on plant safety or any evaluations or conclusions contained in the Safety Evaluation.
There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact Michael A. Brown at (423) 751-3275.
E. K. Henderson Director, Nuclear Regulatory Affairs cc:
NRC  Regional Administrator - Region II NRC  Senior Resident Inspector - Browns Ferry Nuclear Plant NRC  Project Manager - Browns Ferry Nuclear Plant NRC  Branch Chief - Region II}}